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Sample records for asms2004 session code

  1. 76 FR 36231 - American Society of Mechanical Engineers (ASME) Codes and New and Revised ASME Code Cases

    Science.gov (United States)

    2011-06-21

    ...The NRC is amending its regulations to incorporate by reference the 2005 Addenda (July 1, 2005) and 2006 Addenda (July 1, 2006) to the 2004 ASME Boiler and Pressure Vessel Code, Section III, Division 1; 2007 ASME Boiler and Pressure Vessel Code, Section III, Division 1, 2007 Edition (July 1, 2007), with 2008a Addenda (July 1, 2008); 2005 Addenda (July 1, 2005) and 2006 Addenda (July 1, 2006) to the 2004 ASME Boiler and Pressure Vessel Code, Section XI, Division 1; 2007 ASME Boiler and Pressure Vessel Code, Section XI, Division 1, 2007 Edition (July 1, 2007), with 2008a Addenda (July 1, 2008); and 2005 Addenda, ASME OMa Code-2005 (approved July 8, 2005) and 2006 Addenda, ASME OMb Code-2006 (approved July 6, 2006) to the 2004 ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The NRC is also incorporating by reference (with conditions on their use) ASME Boiler and Pressure Vessel Code Case N-722-1, ``Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Section XI, Division 1,'' Supplement 8, ASME approval date: January 26, 2009, and ASME Boiler and Pressure Vessel Code Case N-770-1, ``Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities, Section XI, Division 1,'' ASME approval date: December 25, 2009.

  2. 75 FR 24323 - American Society of Mechanical Engineers (ASME) Codes and New and Revised ASME Code Cases

    Science.gov (United States)

    2010-05-04

    ...The NRC proposes to amend its regulations to incorporate by reference the 2005 Addenda through 2008 Addenda of Section III, Division 1, and the 2005 Addenda through 2008 Addenda of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code (ASME B&PV Code); and the 2005 Addenda and 2006 Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code). The NRC also proposes to incorporate by reference ASME Code Case N-722-1, ``Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials Section XI, Division 1,'' and Code Case N-770, ``Alternative Examination Requirements and Acceptance Standards for Class 1 PWR [Pressurized- Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material with or without Application of Listed Mitigation Activities.''

  3. Nondestructive testing standards and the ASME code

    International Nuclear Information System (INIS)

    Spanner, J.C.

    1991-04-01

    Nondestructive testing (NDT) requirements and standards are an important part of the ASME Boiler and Pressure Vessel Code. In this paper, the evolution of these requirements and standards is reviewed in the context of the unique technical and legal stature of the ASME Code. The coherent and consistent manner by which the ASME Code rules are organized is described, and the interrelationship between the various ASME Code sections, the piping codes, and the ASTM Standards is discussed. Significant changes occurred in ASME Sections 5 and 11 during the 1980s, and these are highlighted along with projections and comments regarding future trends and changes in these important documents. 4 refs., 8 tabs

  4. The ASME Code today -- Challenges, threats, opportunities

    International Nuclear Information System (INIS)

    Canonico, D.A.

    1995-01-01

    Since its modest beginning as a single volume in 1914 the ASME Code, or some of its parts, is recognized today in 48 of the United States and all providence's of Canada. The ASME Code today is composed of 25 books including two Code Case books. These books cover the new construction of boilers and pressure vessels and the new construction and In-Service-Inspection of Nuclear Power Plant components. The ASME accredits all manufacturers of boilers and pressure vessels built to the ASME Code. There are approximately 7650 symbol stamps issued throughout the world. Over 23% of the symbol stamps have been issued outside the USA and Canada. The challenge to the ASME Code is to be accepted as the world standard for pressure boundary components. There are activities underway to achieve that goal. The ASME Code is being revised to make it a more friendly document to entities outside of North America. To achieve that end there are specific tasks underway which are described here

  5. International Accreditation of ASME Codes and Standards

    International Nuclear Information System (INIS)

    Green, Mervin R.

    1989-01-01

    ASME established a Boiler Code Committee to develop rules for the design, fabrication and inspection of boilers. This year we recognize 75 years of that Code and will publish a history of that 75 years. The first Code and subsequent editions provided for a Code Symbol Stamp or mark which could be affixed by a manufacturer to a newly constructed product to certify that the manufacturer had designed, fabricated and had inspected it in accordance with Code requirements. The purpose of the ASME Mark is to identify those boilers that meet ASME Boiler and Pressure Vessel Code requirements. Through thousands of updates over the years, the Code has been revised to reflect technological advances and changing safety needs. Its scope has been broadened from boilers to include pressure vessels, nuclear components and systems. Proposed revisions to the Code are published for public review and comment four times per year and revisions and interpretations are published annually; it's a living and constantly evolving Code. You and your organizations are a vital part of the feedback system that keeps the Code alive. Because of this dynamic Code, we no longer have columns in newspapers listing boiler explosions. Nevertheless, it has been argued recently that ASME should go further in internationalizing its Code. Specifically, representatives of several countries, have suggested that ASME delegate to them responsibility for Code implementation within their national boundaries. The question is, thus, posed: Has the time come to franchise responsibility for administration of ASME's Code accreditation programs to foreign entities or, perhaps, 'institutes.' And if so, how should this be accomplished?

  6. Globalization of ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    Swayne, Rick; Erler, Bryan A.

    2006-01-01

    With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

  7. ASME Code requirements for multi-canister overpack design and fabrication

    International Nuclear Information System (INIS)

    SMITH, K.E.

    1998-01-01

    The baseline requirements for the design and fabrication of the MCO include the application of the technical requirements of the ASME Code, Section III, Subsection NB for containment and Section III, Subsection NG for criticality control. ASME Code administrative requirements, which have not historically been applied at the Hanford site and which have not been required by the US Nuclear Regulatory Commission (NRC) for licensed spent fuel casks/canisters, were not invoked for the MCO. As a result of recommendations made from an ASME Code consultant in response to DNFSB staff concerns regarding ASME Code application, the SNF Project will be making the following modifications: issue an ASME Code Design Specification and Design Report, certified by a Registered Professional Engineer; Require the MCO fabricator to hold ASME Section III or Section VIII, Division 2 accreditation; and Use ASME Authorized Inspectors for MCO fabrication. Incorporation of these modifications will ensure that the MCO is designed and fabricated in accordance with the ASME Code. Code Stamping has not been a requirement at the Hanford site, nor for NRC licensed spent fuel casks/canisters, but will be considered if determined to be economically justified

  8. ASME nuclear codes and standards risk management strategic planning

    International Nuclear Information System (INIS)

    Hill, Ralph S. III; Balkey, Kenneth R.; Erler, Bryan A.; Wesley Rowley, C.

    2007-01-01

    This paper is prepared in honor and in memory of the late Professor Emeritus Yasuhide Asada to recognize his contributions to ASME Nuclear Codes and Standards initiatives, particularly those related to risk-informed technology and System Based Code developments. For nearly two decades, numerous risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to properly manage the numerous initiatives currently underway or planned for the future, the ASME Board on Nuclear Codes and Standards (BNCS) has an established Risk Management Strategic Plan (Plan) that is maintained and updated by the ASME BNCS Risk Management Task Group. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent probabilistic risk assessment (PRA) standards developments for nuclear power plant applications. The paper discusses planned applications within ASME Nuclear Codes and Standards that will require expansion of the ASME PRA Standard to support new advanced light water reactor and next generation reactor developments, such as for high temperature gas-cooled reactors. Emerging regulatory developments related to risk-informed, performance- based approaches are summarized. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is also summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, including related U.S. regulatory activities. (author)

  9. ASME nuclear codes and standards risk management strategic plan

    International Nuclear Information System (INIS)

    Balkey, Kenneth R.

    2003-01-01

    Over the past 15 years, several risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to better manage the numerous initiatives in the future, the ASME Board on Nuclear Codes and Standards has recently developed and approved a Risk Management Strategic Plan. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent issuance of the ASME Standard for Probabilistic Risk Assessment (PRA) for Nuclear Power Plant Applications. The paper discusses potential applications within ASME Nuclear Codes and Standards that may require expansion of the PRA Standard, such as for new generation reactors, or the development of new PRA Standards. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, and related U.S. regulatory activities are also summarized. (author)

  10. ASME Code Efforts Supporting HTGRs

    Energy Technology Data Exchange (ETDEWEB)

    D.K. Morton

    2012-09-01

    In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.

  11. ASME Code Efforts Supporting HTGRs

    Energy Technology Data Exchange (ETDEWEB)

    D.K. Morton

    2011-09-01

    In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.

  12. Report on the Current Technical Issues on ASME Nuclear Code and Standard

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2008-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  13. Consideration of the Construction Code for TBM-body in ASME BPVC

    International Nuclear Information System (INIS)

    Kim, Dongjun; Kim, Yunjae; Kim, Suk Kwon; Park, Sung Dae; Lee, Dong Won

    2016-01-01

    In this paper, ASME code is briefly introduced, and the TBM-body is classified for selecting the ASME section. With the classification of TBM-body, the appropriate section is determined. Helium Cooled Ceramic Reflector (HCCR) Test Blanket System (TBS) has been designed to research on the functions of breeding blanket by KO TBM team. The functions has three subjects as 1) Tritium breeding, 2) Heat conversion and extraction, and 3) Neutron and Gamma-ray shielding. For the process of design, it is needed to select the appropriate construction code as the design criteria. ITER Organization (IO) has proposed that RCC-MR Edition 2007 ver. shall be used for TBM-shield. Because the TBM-shield is connected to the vacuum boundary. For the other part of TBM-set, TBM-body, there is no constraint on the selected code, and the manufacturer can appropriately select the construction code to apply design and fabrication parts. KO TBM Team has considered whether it is appropriate to choose any code for TBM-body. One of the things is ASME code. The advantage of ASME choice is suitable to the domestic status. In the domestic nuclear plant, ASME or KEPIC code is used as regulatory requirements. Based on this, it is possible to prepare a domestic fusion plant regulatory. In this paper, the construction code of TBM-body was determined in ASME BPVC. For the determination of code, the structure of ASME BPVC was introduced and the classification for TBM-body was conducted by the ITER criteria. And the operation conditions of TBM-body that contained creep and irradiation effects was considered to determine the construction code

  14. Consideration of the Construction Code for TBM-body in ASME BPVC

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dongjun; Kim, Yunjae [Korea Univ., Seoul (Korea, Republic of); Kim, Suk Kwon; Park, Sung Dae; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, ASME code is briefly introduced, and the TBM-body is classified for selecting the ASME section. With the classification of TBM-body, the appropriate section is determined. Helium Cooled Ceramic Reflector (HCCR) Test Blanket System (TBS) has been designed to research on the functions of breeding blanket by KO TBM team. The functions has three subjects as 1) Tritium breeding, 2) Heat conversion and extraction, and 3) Neutron and Gamma-ray shielding. For the process of design, it is needed to select the appropriate construction code as the design criteria. ITER Organization (IO) has proposed that RCC-MR Edition 2007 ver. shall be used for TBM-shield. Because the TBM-shield is connected to the vacuum boundary. For the other part of TBM-set, TBM-body, there is no constraint on the selected code, and the manufacturer can appropriately select the construction code to apply design and fabrication parts. KO TBM Team has considered whether it is appropriate to choose any code for TBM-body. One of the things is ASME code. The advantage of ASME choice is suitable to the domestic status. In the domestic nuclear plant, ASME or KEPIC code is used as regulatory requirements. Based on this, it is possible to prepare a domestic fusion plant regulatory. In this paper, the construction code of TBM-body was determined in ASME BPVC. For the determination of code, the structure of ASME BPVC was introduced and the classification for TBM-body was conducted by the ITER criteria. And the operation conditions of TBM-body that contained creep and irradiation effects was considered to determine the construction code.

  15. ASME nuclear codes and standards: Recent technical initiatives

    International Nuclear Information System (INIS)

    Feigel, R. E.

    1995-01-01

    Although nuclear power construction is currently in a hiatus in the US, ASME and its volunteer committees remain committed to continual improvements in the technical requirements in its nuclear codes. This paper provides an overview of several significant recent revisions to ASME' s nuclear codes. Additionally, other important initiatives currently being addressed by ASME committees will be described. With the largest population of operating light water nuclear plants in the world and worldwide use of its nuclear codes, ASME continues to support technical advancements in its nuclear codes and standards. While revisions of various magnitude are an ongoing process, several recent revisions embody significant changes based on state of the art design philosophy and substantial industry experience. In the design area, a significant revisions has recently been approved which will significantly reduce conservatisms in seismic piping design as well as provide simplified design rules. Major revisions have also been made to the requirements for nuclear material manufacturers and suppliers, which should result in clearer understanding of this difficult administrative area of the code. In the area of Section XI inservice rules, substantial studies are underway to investigate the application of probabilistic, risked based inspection in lieu of the current deterministic inspection philosophy. While much work still is required in this area, it is an important potential application of the emerging field of risk based inspection

  16. Evaluation of practicality of ASME code, Section XI

    International Nuclear Information System (INIS)

    Mattu, R.K.; Lauderdale, J.R.; Liu, S.N.; Lance, J.J.

    2004-01-01

    Many nuclear power plants have found that it is impractical or unduly burdensome to comply with some ASME Boiler and Pressure Code provisions and have sought relief from those provisions from the Nuclear Regulatory Commission. An Electric Power Research Institute (EPRI) project is evaluating such Code provisions and alternatives to them that will meet the safety intent of the Code with less burden on utilities. The methodology is to extract data from an on-line data base of relief requests since 1980, analyse the data to identify burdensome provisions for which there are satisfactory alternatives, and recommend changes in the Code to the ASME. (author)

  17. Recent development in the ASME O and M committee codes, standards, and guides

    International Nuclear Information System (INIS)

    Rowley, C.W.

    1999-01-01

    The ASME O and M Committee continues to expand and update its code, standards, and guides as contained in the ASME OM Code and the ASME OM Standards/Guides. This paper will describe recent changes to these two ASME documents, including technical inquiries, code cases, and the major reformat of the ASME OM Code 1998 Edition. Also two new Parts to the ASME OM S/G will be discussed: OM Part 23 and OM Part 24, which are close to being initially published. A third new Part to the ASME OM S/G has been authorized and has recently started to get organized: Part 26, 'Thermal Calibration of RTDs'. In addition this paper will describe the future plans for these two documents as provided in the O and M Committee Strategic Plan. (author)

  18. Operating nuclear plant feedback to ASME and French codes

    International Nuclear Information System (INIS)

    Journet, J.; O'Donnell, W.J.

    1996-01-01

    The French have an advantage in nuclear plant operating experience feedback due to the highly centralized nature of their nuclear industry. There is only one utility in charge of design as well as operations (EDF) and only one reactor vendor (Framatome). The ASME Code has played a key role in resolving technical issues in the design and operation of nuclear plants since the inception of nuclear power. The committee structure of the Code brings an ideal combination of senior technical people with both broad and specialized experience to bear on complex how safe is safe enough technical issues. The authors now see an even greater role for the ASME Code in a proposed new regulatory era for the US nuclear industry. The current legalistic confrontational regulatory era has been quite destructive. There now appears to be a real opportunity to begin a new era of technical consensus as the primary means for resolving safety issues. This change can quickly be brought about by having the industry take operating plant problems and regulatory technical issues directly to the ASME Code for timely resolution. Surprisingly, there is no institution in the US nuclear industry with such a mandate. In fact, the industry is organized to feedback through the Nuclear Regulatory Commission issues which could be far better resolved through the ASME Code. Major regulatory benefits can be achieved by closing this loop and providing systematic interaction with the ASME Code. The essential elements of a new regulatory era and ideas for organizing US institutional industry responsibilities, taken from the French experience, are described in this paper

  19. ASME nuclear codes and standards: Scope of coverage and current initiatives

    International Nuclear Information System (INIS)

    Eisenberg, G. M.

    1995-01-01

    The objective of this paper is to address the broad scope of coverage of nuclear codes, standards and guides produced and administered by the American Society of Mechanical Engineers (ASME). Background information is provided regarding the evolution of the present activities. Details are provided on current initiatives intended to permit ASME to meet the needs of a changing nuclear industry on a worldwide scale. During the early years of commercial nuclear power, ASME produced a code for the construction of nuclear vessels used in the reactor coolant pressure boundary, containment and auxiliary systems. In response to industry growth, ASME Code coverage soon broadened to include rules for construction of other nuclear components, and inservice inspection of nuclear reactor coolant systems. In the years following this, the scope of ASME nuclear codes, standards and guides has been broadened significantly to include air cleaning activities for nuclear power reactors, operation and maintenance of nuclear power plants, quality assurance programs, cranes for nuclear facilities, qualification of mechanical equipment, and concrete reactor vessels and containments. ASME focuses on globalization of its codes, standards and guides by encouraging and promoting their use in the international community and by actively seeking participation of international members on its technical and supervisory committees and in accreditation activities. Details are provided on current international representation. Initiatives are underway to separate the technical requirements from administrative and enforcement requirements, to convert to hard metric units, to provide for non-U. S. materials, and to provide for translations into non-English languages. ASME activity as an accredited ISO 9000 registrar for suppliers of mechanical equipment is described. Rules are being developed for construction of containment systems for nuclear spent fuel and high-level waste transport packagings. Intensive

  20. Significant issues and changes for ANSI/ASME OM-1 1981, part 1, ASME OMc code-1994, and ASME OM Code-1995, Appendix I, inservice testing of pressure relief devices in light water reactor power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seniuk, P.J.

    1996-12-01

    This paper identifies significant changes to the ANSI/ASME OM-1 1981, Part 1, and ASME Omc Code-1994 and ASME OM Code-1995, Appendix I, {open_quotes}Inservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants{close_quotes}. The paper describes changes to different Code editions and presents insights into the direction of the code committee and selected topics to be considered by the ASME O&M Working Group on pressure relief devices. These topics include scope issues, thermal relief valve issues, as-found and as-left set-pressure determinations, exclusions from testing, and cold setpoint bench testing. The purpose of this paper is to describe some significant issues being addressed by the O&M Working Group on Pressure Relief Devices (OM-1). The writer is currently the chair of OM-1 and the statements expressed herein represents his personal opinion.

  1. Significant issues and changes for ANSI/ASME OM-1 1981, part 1, ASME OMc code-1994, and ASME OM Code-1995, Appendix I, inservice testing of pressure relief devices in light water reactor power plants

    International Nuclear Information System (INIS)

    Seniuk, P.J.

    1996-01-01

    This paper identifies significant changes to the ANSI/ASME OM-1 1981, Part 1, and ASME Omc Code-1994 and ASME OM Code-1995, Appendix I, open-quotes Inservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plantsclose quotes. The paper describes changes to different Code editions and presents insights into the direction of the code committee and selected topics to be considered by the ASME O ampersand M Working Group on pressure relief devices. These topics include scope issues, thermal relief valve issues, as-found and as-left set-pressure determinations, exclusions from testing, and cold setpoint bench testing. The purpose of this paper is to describe some significant issues being addressed by the O ampersand M Working Group on Pressure Relief Devices (OM-1). The writer is currently the chair of OM-1 and the statements expressed herein represents his personal opinion

  2. Passport of global nuclear business. ASME code certificate acquirement and inspection practices

    International Nuclear Information System (INIS)

    Kawabata, Hiroyuki; Terajima, Makoto; Anami, Kazuhiro

    2010-01-01

    There are possibilities of Japanese nuclear industries to participate in global business such as new and additional construction of nuclear power plants in US and also Asian and other developing countries in the world. It is requisite to acquire ASME code certificate for global business participation, just as passport. This article consists of five papers on present status of ASME code certificate acquirement and inspection practices of nuclear components vendors in the area of Japanese nuclear business. Activities of JSME Committee on Power Generation Facility Codes to make JSME codes corresponded to ASME nuclear codes and standards for their international deployment are also described. (T. Tanaka)

  3. Analysis of preservice inspection relief requests and recommendations for ASME code changes

    International Nuclear Information System (INIS)

    Cook, J.F.

    1985-05-01

    NRC regulations require that preservice inspection (PSI) of nuclear plants be performed in accordance with referenced editions and addenda of Division 1 rules of Section XI, ''Rules for Inservice Inspection of Nuclear Power Plant Components'', of the ASME Boiler and Pressure Vessel Code (ASME Code). The regulations permit applicants to request and obtain relief from the NRC from specific ASME Code requirements that are determined to be impractical. Applicant requests for relief from preservice inspection (PSI) requirements were compiled and analyzed. From this data, covering a total of 178 relief requests, common problems with examination requirements were identified. Changes to examination requirements to solve selected problems are proposed. By following later ASME Code requirements, 46 out of the 178 relief requests can be eliminated. Implementing proposed Code changes would eliminate another 25 relief requests, leaving 107 relief requests out of the original 178 relief requests covered by this survey

  4. Review of ASME nuclear codes and standards- subcommittee on repairs, replacements, and modifications

    International Nuclear Information System (INIS)

    Mawson, T.J.

    1990-01-01

    As requested by the ASME board on Nuclear Codes and Standards, the Pressure Vessel Research Committee initiated a project to review Sections III and XI of the ASME Boiler and Pressure Vessel Code for the purposes of improving, clarifying, providing transition, consistency, compatibility, and simplifying code requirements. The project was organized with six subcommittees to address various Code activities: design; tests and examinations; documentation; quality assurance; repair, replacement and modification; and general requirements. This paper discusses how the subcommittee on repair, replacement and modification was organized to review the repair, replacement and modification requirements of the ASME boiler and pressure vessel code, Section III and Section XI for Class 1, 2, and 3 and MC components and their supports, and other documents of the nuclear industry related to the repair, replacement and modification requirements of the ASME code

  5. Computer Program of SIE ASME-NH (Revision 1.0) Code

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, J. H

    2008-01-15

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

  6. Computer Program of SIE ASME-NH (Revision 1.0) Code

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, J. H.

    2008-01-01

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail

  7. Estimates of margins in ASME Code strength values for stainless steel nuclear piping

    International Nuclear Information System (INIS)

    Ware, A.G.

    1995-01-01

    The margins in the ASME Code stainless steel allowable stress values that can be attributed to the variations in material strength are evaluated for nuclear piping steels. Best-fit curves were calculated for the material test data that were used to determine allowable stress values for stainless steels in the ASME Code, supplemented by more recent data, to estimate the mean stresses. The mean yield stresses (on which the stainless steel S m values are based) from the test data are about 15 to 20% greater than the ASME Code yield stress values. The ASME Code yield stress values are estimated to approximately coincide with the 97% confidence limit from the test data. The mean and 97% confidence limit values can be used in the probabilistic risk assessments of nuclear piping

  8. Future direction of ASME nuclear codes and standards

    International Nuclear Information System (INIS)

    Ennis, Kevin; Sheehan, Mark E.

    2003-01-01

    While the nuclear power industry in the US is in a period of stasis, there continues to be a great deal of activity in the ASME nuclear standards development arena. As plants age, the need for new approaches in standardization changes with the changing needs of the industry. New tools are becoming available in the form of risk analysis, and this is finding its way into more and more of ASME's standards activities. This paper will take a look at the direction that ASME nuclear Codes and Standards are heading in this and other areas, as well as taking a look at some advance reactor concepts and plans for standards to address new technologies

  9. Inservice inspection procedures and training according to the ASME code

    International Nuclear Information System (INIS)

    Greenwald, S.M.; Chockie, L.J.

    1987-01-01

    Mandatory training of the technical staff at a nuclear power plant is of paramount importance if we are to avoid costly plant shutdowns. This training should include the requirements for both Preservice and Inservice Inspection, in addition to Quality Assurance procedures as required by the American Society of Mechanical Engineers (ASME) Code. The training is best accomplished by utilizing instructors who are thoroughly familiar with plant operations and the ASME Code, as well as serving on one of the Code committees. This paper focuses on the Inservice Inspection procedures and the results of an intensive training effort to implement such procedures. (author)

  10. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  11. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-15

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  12. Design Procedure of Graphite Components by ASME HTR Codes

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Ji-Ho; Jo, Chang Keun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this study, the ASME B and PV Code, Subsection HH, Subpart A, design procedure for graphite components of HTRs was reviewed and the differences from metal materials were remarked. The Korean VHTR has a prismatic core which is made of multiple graphite blocks, reflectors, and core supports. One of the design issues is the assessment of the structural integrity of the graphite components because the graphite is brittle and shows quite different behaviors from metals in high temperature environment. The American Society of Mechanical Engineers (ASME) issued the latest edition of the code for the high temperature reactors (HTR) in 2015. In this study, the ASME B and PV Code, Subsection HH, Subpart A, Graphite Materials was reviewed and the special features were remarked. Due the brittleness of graphites, the damage-tolerant design procedures different from the conventional metals were adopted based on semi-probabilistic approaches. The unique additional classification, SRC, is allotted to the graphite components and the full 3-D FEM or equivalent stress analysis method is required. In specific conditions, the oxidation and viscoelasticity analysis of material are required. The fatigue damage rule has not been established yet.

  13. Design Procedure of Graphite Components by ASME HTR Codes

    International Nuclear Information System (INIS)

    Kang, Ji-Ho; Jo, Chang Keun

    2016-01-01

    In this study, the ASME B and PV Code, Subsection HH, Subpart A, design procedure for graphite components of HTRs was reviewed and the differences from metal materials were remarked. The Korean VHTR has a prismatic core which is made of multiple graphite blocks, reflectors, and core supports. One of the design issues is the assessment of the structural integrity of the graphite components because the graphite is brittle and shows quite different behaviors from metals in high temperature environment. The American Society of Mechanical Engineers (ASME) issued the latest edition of the code for the high temperature reactors (HTR) in 2015. In this study, the ASME B and PV Code, Subsection HH, Subpart A, Graphite Materials was reviewed and the special features were remarked. Due the brittleness of graphites, the damage-tolerant design procedures different from the conventional metals were adopted based on semi-probabilistic approaches. The unique additional classification, SRC, is allotted to the graphite components and the full 3-D FEM or equivalent stress analysis method is required. In specific conditions, the oxidation and viscoelasticity analysis of material are required. The fatigue damage rule has not been established yet

  14. Assessment of ASME code examinations on regenerative, letdown and residual heat removal heat exchangers

    International Nuclear Information System (INIS)

    Gosselin, Stephen R.; Cumblidge, Stephen E.; Anderson, Michael T.; Simonen, Fredric A.; Tinsley, G A.; Lydell, B.; Doctor, Steven R.

    2005-01-01

    Inservice inspection requirements for pressure retaining welds in the regenerative, letdown, and residual heat removal heat exchangers are prescribed in Section XI Articles IWB and IWC of the ASME Boiler and Pressure Vessel Code. Accordingly, volumetric and/or surface examinations are performed on heat exchanger shell, head, nozzle-to-head, and nozzle-to-shell welds. Inspection difficulties associated with the implementation of these Code-required examinations have forced operating nuclear power plants to seek relief from the U.S. Nuclear Regulatory Commission. The nature of these relief requests are generally concerned with metallurgical, geometry, accessibility, and radiation burden. Over 60% of licensee requests to the NRC identify significant radiation exposure burden as the principle reason for relief from the ASME Code examinations on regenerative heat exchangers. For the residual heat removal heat exchangers, 90% of the relief requests are associated with geometry and accessibility concerns. Pacific Northwest National Laboratory was funded by the NRC Office of Nuclear Regulatory Research to review current practice with regard to volumetric and/or surface examinations of shell welds of letdown heat exchangers regenerative heat exchangers and residual (decay) heat removal heat exchangers Design, operating, common preventative maintenance practices, and potential degradation mechanisms are reviewed. A detailed survey of domestic and international PWR-specific operating experience was performed to identify pressure boundary failures (or lack of failures) in each heat exchanger type and NSSS design. The service data survey was based on the PIPExp- database and covers PWR plants worldwide for the period 1970-2004. Finally a risk assessment of the current ASME Code inspection requirements for residual heat removal, letdown, and regenerative heat exchangers is performed. The results are then reviewed to discuss the examinations relative to plant safety and

  15. Regulatory Endorsement Activities for ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    West, Raymond A.

    2006-01-01

    The ASME Board on Nuclear Codes and Standards (BNCS) has formed a Task Group on Regulatory Endorsement (TG-RE) that is currently in discussions with the United States Nuclear Regulatory Commission (NRC) to look at suggestions and recommendations that can be used to help with the endorsement of new and revised ASME Nuclear Codes and Standards (NC and S). With the coming of new reactors in the USA in the very near future we need to look at both the regulations and all the ASME NC and S to determine where we need to make changes to support these new plants. At the same time it is important that we maintain our operating plants while addressing ageing management needs of our existing reactors. This is going to take new thinking, time, resources, and money. For all this to take place the regulations and requirements that we use must be clear concise and necessary for safety and to that end both the NRC and ASME are working together to make this happen. Because of the influence that the USA has in the world in dealing with these issues, this paper is written to inform the international nuclear engineering community about the issues and what actions are being addressed under this effort. (author)

  16. Researching on knowledge architecture of design by analysis based on ASME code

    International Nuclear Information System (INIS)

    Bao Shiyi; Zhou Yu; He Shuyan

    2003-01-01

    The quality of knowledge-based system's knowledge architecture is one of decisive factors of knowledge-based system's validity and rationality. For designing the ASME code knowledge based system, this paper presents a knowledge acquisition method which is extracting knowledge through document analysis consulted domain experts' knowledge. Then the paper describes knowledge architecture of design by analysis based on the related rules in ASME code. The knowledge of the knowledge architecture is divided into two categories: one is empirical knowledge, and another is ASME code knowledge. Applied as the basement of the knowledge architecture, a general procedural process of design by analysis that is met the engineering design requirements and designers' conventional mode is generalized and explained detailed in the paper. For the sake of improving inference efficiency and concurrent computation of KBS, a kind of knowledge Petri net (KPN) model is proposed and adopted in expressing the knowledge architecture. Furthermore, for validating and verifying of the empirical rules, five knowledge validation and verification theorems are given in the paper. Moreover the research production is applicable to design the knowledge architecture of ASME codes or other engineering standards. (author)

  17. Technical justification for ASME code section xi crack detection by visual examination

    International Nuclear Information System (INIS)

    Nickell, R.E.; Rashid, Y.R.

    2001-01-01

    A critical technical element of nuclear power plant license renewal in the United States is the demonstration that the effects of aging do not compromise the intended safety function(s) of a system, structure, or component during the extended term of operation. The demonstration may take either of two forms. First, it can be shown that the design basis for the system, structure, or component is sufficiently robust that the aging effects have been insignificant through the current license term, and will continue to be insignificant through the extended term. Alternatively, it can be shown that, while the aging effects may be potentially significant, those effects can be managed and functionality maintained by defined programmatic activities during the extended term of operation. The first of the two approaches is generally provided by the construction basis, such as construction in accordance with the ASME Code Section III and other consensus codes and standards. The second of the two approaches is often provided by periodic inservice inspection and testing, in accordance with the ASME Code Section XI. The purpose of the ASME Section XI inspections and tests is to assure that systems, components, and structures are fit for continued service until the next scheduled inspection or test. The purpose of this paper is to document the effectiveness of the current ASME Code Section XI visual examination procedures in detecting the effects of aging for systems, structures, and components that are tolerant of mature cracks. (author)

  18. Basic requirements of mechanical properties for nuclear pressure vessel materials in ASME-BPV code

    International Nuclear Information System (INIS)

    Ning Dong; Yao Weida

    2011-01-01

    The four basic aspects of strengths, ductility, toughness and fatigue strengths can be summarized for overall mechanical properties requirements of materials for nuclear pressure-retaining vessels in ASME-BPV code. These mechanical property indexes involve in the factors of melting, manufacture, delivery conditions, check or recheck for mechanical properties and chemical compositions, etc. and relate to degradation and damage accumulation during the use of materials. This paper specifically accounts for the basic requirements and theoretic basis of mechanical properties for nuclear pressure vessel materials in ASME-BPV code and states the internal mutual relationships among the four aspects of mechanical properties. This paper focuses on putting forward at several problems on mechanical properties of materials that shall be concerned about during design and manufacture for nuclear pressure vessels according to ASME-BPV code. (author)

  19. Code cases for implementing risk-based inservice testing in the ASME OM code

    International Nuclear Information System (INIS)

    Rowley, C.W.

    1996-01-01

    Historically inservice testing has been reasonably effective, but quite costly. Recent applications of plant PRAs to the scope of the IST program have demonstrated that of the 30 pumps and 500 valves in the typical plant IST program, less than half of the pumps and ten percent of the valves are risk significant. The way the ASME plans to tackle this overly-conservative scope for IST components is to use the PRA and plant expert panels to create a two tier IST component categorization scheme. The PRA provides the quantitative risk information and the plant expert panel blends the quantitative and deterministic information to place the IST component into one of two categories: More Safety Significant Component (MSSC) or Less Safety Significant Component (LSSC). With all the pumps and valves in the IST program placed in MSSC or LSSC categories, two different testing strategies will be applied. The testing strategies will be unique for the type of component, such as centrifugal pump, positive displacement pump, MOV, AOV, SOV, SRV, PORV, HOV, CV, and MV. A series of OM Code Cases are being developed to capture this process for a plant to use. One Code Case will be for Component Importance Ranking. The remaining Code Cases will develop the MSSC and LSSC testing strategy for type of component. These Code Cases are planned for publication in early 1997. Later, after some industry application of the Code Cases, the alternative Code Case requirements will gravitate to the ASME OM Code as appendices

  20. Code cases for implementing risk-based inservice testing in the ASME OM code

    Energy Technology Data Exchange (ETDEWEB)

    Rowley, C.W.

    1996-12-01

    Historically inservice testing has been reasonably effective, but quite costly. Recent applications of plant PRAs to the scope of the IST program have demonstrated that of the 30 pumps and 500 valves in the typical plant IST program, less than half of the pumps and ten percent of the valves are risk significant. The way the ASME plans to tackle this overly-conservative scope for IST components is to use the PRA and plant expert panels to create a two tier IST component categorization scheme. The PRA provides the quantitative risk information and the plant expert panel blends the quantitative and deterministic information to place the IST component into one of two categories: More Safety Significant Component (MSSC) or Less Safety Significant Component (LSSC). With all the pumps and valves in the IST program placed in MSSC or LSSC categories, two different testing strategies will be applied. The testing strategies will be unique for the type of component, such as centrifugal pump, positive displacement pump, MOV, AOV, SOV, SRV, PORV, HOV, CV, and MV. A series of OM Code Cases are being developed to capture this process for a plant to use. One Code Case will be for Component Importance Ranking. The remaining Code Cases will develop the MSSC and LSSC testing strategy for type of component. These Code Cases are planned for publication in early 1997. Later, after some industry application of the Code Cases, the alternative Code Case requirements will gravitate to the ASME OM Code as appendices.

  1. A study on technical issues of materials and design bases in ASME section III subsection NH code

    International Nuclear Information System (INIS)

    Lee, Hyeong Yeon; Kim, Jong Bum; Yoo, Bong

    2000-12-01

    In this study, an analysis of evaluation report by ORNL on the technical issues of elevated temperatures design guide line, ASME Code Section III Subsection NH was conducted and a brief evaluation procedure of the creep-fatigue damage was presented. ORNL published the report in 1993 and reviewed the issue areas where code rules or regulatory guides may be lacking or inadequate to ensure safe operation over the expected life cycles for liquid metal reactor systems. From historical viewpoint of the ASME NH code development, ASME Code Case 47 was changed much in 1989 edition, which includes the stress relaxation behavior in creep damage evaluation. Afterwards the 1992 version of CC N-47 was upgraded to Subsection NH in 1995 edition, which is the same with that of CC N-47 1992 edition except few material data. This report brings up the technical and regulatory issues that can not guarantee the safe and reliable operation of the ALMR which got the conceptual design certification from NRC. Twenty three technical issues were raised and settlement methodology were proposed. Additionally, the status of items approved by ASME code subgroup of elevated temperature design committee for the revision of the most recent 1998 edition of ASME NH was described

  2. Development of ASME Code Section 11 visual examination requirements

    International Nuclear Information System (INIS)

    Cook, J.F.

    1990-01-01

    Section XI of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) defines three types of nondestructive examinations, visual, surface, and volumetric. Visual examination is important since it is the primary examination method for many safety-related components and systems and is also used as a backup examination for the components and systems which receive surface or volumetric examinations. Recent activity in the Section XI Code organization to improve the rules for visual examinations is reviewed and the technical basis for the new rules, which cover illumination, vision acuity, and performance demonstration, is explained

  3. Assessment of induction elbows for an ASME Code application

    International Nuclear Information System (INIS)

    Panesar, J.S.; Soliman, M.

    1991-01-01

    The ASME Nuclear Codes impose some specific requirements on the wall thickness uniformity and the out-of-roundness of cross sections of the elbows for Nuclear Power Plant applications. Due to some of these requirements, manufacturing and installation of these elbows can be time consuming and quite expensive. This paper explores the feasibility of using induction elbows for nuclear application from the stress analysis point of view. To this end, three different sizes of 90deg elbows have been analyzed based on the geometry of an 'ASME Code' elbow and an elbow formed by induction bending. The analysis is carried out for internal pressure, in-plane and out-of-plane loads. Based on the results of these three carbon steel elbows, the use of induction elbows in some of the CANDU-PHW (CANadian Deuterium Uranium-Pressurized Heavy Water) power plant applications seems encouraging. However, before the feasibility can be fully confirmed analysis and induction bending tests over a wider range of geometries, loading conditions, and materials are required. (author)

  4. Inelasticity and the ASME code

    International Nuclear Information System (INIS)

    Berman, I.

    1978-01-01

    Although it may have more general applicability, this paper is specifically concerned with some aspects of plasticity for class I nuclear components that are contained in section III of the ASME Boiler and Pressure Vessel Code. It directly addresses design for components at temperatures at which creep is not a factor. A review is made of the relationship of plasticity to each of the three failure modes that the stress limits are intended to prevent. It is found that the prevention of bursting and gross distortion from a single application of pressure and the prevention of fatigue failure caused by repeated cycles of peak stresses are well supported by experimental results. The experimental verification for the rules to show that the primary plus secondary stresses shakedown to elastic behavior is not clear. Various directed efforts which could lead to greater assurance of shakedown to elastic behavior are suggested. The major approach should be a massive program to develop a test matrix of experimental information for various portions of each component of interest in the Code. (Auth.)

  5. Comparative evaluation of structural integrity for ITER blanket shield block based on SDC-IC and ASME code

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Hee-Jin [ITER Korea, National Fusion Research Institute, 169-148 Gwahak-Ro, Yuseong-Gu, Daejeon (Korea, Republic of); Ha, Min-Su, E-mail: msha12@nfri.re.kr [ITER Korea, National Fusion Research Institute, 169-148 Gwahak-Ro, Yuseong-Gu, Daejeon (Korea, Republic of); Kim, Sa-Woong; Jung, Hun-Chea [ITER Korea, National Fusion Research Institute, 169-148 Gwahak-Ro, Yuseong-Gu, Daejeon (Korea, Republic of); Kim, Duck-Hoi [ITER Organization, Route de Vinon sur Verdon - CS 90046, 13067 Sant Paul Lez Durance (France)

    2016-11-01

    Highlights: • The procedure of structural integrity and fatigue assessment was described. • Case studies were performed according to both SDC-IC and ASME Sec. • III codes The conservatism of the ASME code was demonstrated. • The study only covers the specifically comparable case about fatigue usage factor. - Abstract: The ITER blanket Shield Block is a bulk structure to absorb radiation and to provide thermal shielding to vacuum vessel and external vessel components, therefore the most significant load for Shield Block is the thermal load. In the previous study, the thermo-mechanical analysis has been performed under the inductive operation as representative loading condition. And the fatigue evaluations were conducted to assure structural integrity for Shield Block according to Structural Design Criteria for In-vessel Components (SDC-IC) which provided by ITER Organization (IO) based on the code of RCC-MR. Generally, ASME code (especially, B&PV Sec. III) is widely applied for design of nuclear components, and is usually well known as more conservative than other specific codes. For the view point of the fatigue assessment, ASME code is very conservative compared with SDC-IC in terms of the reflected K{sub e} factor, design fatigue curve and other factors. Therefore, an accurate fatigue assessment comparison is needed to measure of conservatism. The purpose of this study is to provide the fatigue usage comparison resulting from the specified operating conditions shall be evaluated for Shield Block based on both SDC-IC and ASME code, and to discuss the conservatism of the results.

  6. Comparative evaluation of structural integrity for ITER blanket shield block based on SDC-IC and ASME code

    International Nuclear Information System (INIS)

    Shim, Hee-Jin; Ha, Min-Su; Kim, Sa-Woong; Jung, Hun-Chea; Kim, Duck-Hoi

    2016-01-01

    Highlights: • The procedure of structural integrity and fatigue assessment was described. • Case studies were performed according to both SDC-IC and ASME Sec. • III codes The conservatism of the ASME code was demonstrated. • The study only covers the specifically comparable case about fatigue usage factor. - Abstract: The ITER blanket Shield Block is a bulk structure to absorb radiation and to provide thermal shielding to vacuum vessel and external vessel components, therefore the most significant load for Shield Block is the thermal load. In the previous study, the thermo-mechanical analysis has been performed under the inductive operation as representative loading condition. And the fatigue evaluations were conducted to assure structural integrity for Shield Block according to Structural Design Criteria for In-vessel Components (SDC-IC) which provided by ITER Organization (IO) based on the code of RCC-MR. Generally, ASME code (especially, B&PV Sec. III) is widely applied for design of nuclear components, and is usually well known as more conservative than other specific codes. For the view point of the fatigue assessment, ASME code is very conservative compared with SDC-IC in terms of the reflected K_e factor, design fatigue curve and other factors. Therefore, an accurate fatigue assessment comparison is needed to measure of conservatism. The purpose of this study is to provide the fatigue usage comparison resulting from the specified operating conditions shall be evaluated for Shield Block based on both SDC-IC and ASME code, and to discuss the conservatism of the results.

  7. Recommendations to ASME for code guidelines and criteria for continued operation of equipment

    International Nuclear Information System (INIS)

    Harvey, J.F.

    1993-01-01

    In May 1988, the American Society of Mechanical Engineers, ASME, asked the Pressure Vessel Research Council, PVRC, to review the part it should play in the continued operation of equipment originally designed and fabricated to the ASME codes and rules. This was prompted solely by an economic opportunity in which the capital expenditures to replace plants was far more costly than evaluating, repairing, and extending the nominal design life of the individual component. For instance, nuclear plants are normally designed for a life of 40 years, while fossil fired facilities may have been designed for other time lives, yet at the end of their original design life may actually have many useful years remaining. While this action was economically prompted, it inherently involved a two-fold one; namely, (1) safety, (2) legal. There is no question of safety to operating personnel. While codes for fossil components do not specify design lives, their adoption by many states provides a legal means of procedure in event of a mishap. This recognizes a cradle-to-grave safety responsibility. It is toward maintaining ASMEs leadership as a code authority that this report has been prepared

  8. Review of the margins for ASME code fatigue design curve - effects of surface roughness and material variability

    International Nuclear Information System (INIS)

    Chopra, O. K.; Shack, W. J.

    2003-01-01

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ((var e psilon)-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue (var e psilon)-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the steels. Experimental data are presented on the effects of surface roughness on the fatigue life of these steels in air and LWR environments. Statistical models are presented for estimating the fatigue (var e psilon)-N curves as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the conservatism in the existing ASME Code fatigue evaluations. A critical review of the margins for ASME Code fatigue design curves is presented

  9. Review of the margins for ASME code fatigue design curve - effects of surface roughness and material variability.

    Energy Technology Data Exchange (ETDEWEB)

    Chopra, O. K.; Shack, W. J.; Energy Technology

    2003-10-03

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue {var_epsilon}-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the steels. Experimental data are presented on the effects of surface roughness on the fatigue life of these steels in air and LWR environments. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the conservatism in the existing ASME Code fatigue evaluations. A critical review of the margins for ASME Code fatigue design curves is presented.

  10. Interpretation, with respect to ASME code Case N-318, of limit moment and fatigue tests of lugs welded to pipe

    International Nuclear Information System (INIS)

    Foster, D.C.; Van Duyne, D.A.; Budlong, L.A.; Muffett, J.W.; Wais, E.A.; Streck, G.; Rodabaugh, E.C.

    1990-01-01

    Two nonmandatory ASME code cases have been used often in the evaluation of lugs on nuclear-power- plant piping systems. ASME Code Case N-318 provides guidance for evaluation of the design of rectangular cross-section attachments on Class 2 or 3 piping, and ASME Code Case N-122 provides guidance for evaluation of lugs on Class 1 piping. These code cases have been reviewed and evaluated based on available test data. The results indicate that the Code cases are overly conservative. Recommendations for revisions to the cases are presented which, if adopted, will reduce the overconservatism

  11. Elastic creep-fatigue evaluation for ASME code

    International Nuclear Information System (INIS)

    Severud, L.K.; Winkel, B.V.

    1987-01-01

    Experience with applying the ASME Code Case N-47 rules for evaluation of creep-fatigue with elastic analysis results has been problematic. The new elastic evaluation methods are intended to bound the stress level and strain range values needed for use in employing the code inelastic analysis creep-fatigue damage counting procedures. To account for elastic followup effects, ad hoc rules for stress classification, shakedown, and ratcheting are employed. Because elastic followup, inelastic strain concentration, and stress-time effects are accounted for, the design fatigue curves in Case N-47 for inelastic analysis are used instead of the more conservative elastic analysis curves. Creep damage assessments are made using an envelope stress-time history that treats multiple load events and repeated cycles during elevated temperature service life. (orig./GL)

  12. Approaching application of risk-based inspection to ASME code section XI

    International Nuclear Information System (INIS)

    Hedden, Owen F.

    1995-01-01

    This paper will describe current efforts within the ASME Boiler and Pressure Vessel Committee's Subcommittee on Nuclear Inservice Inspection to introduce risk-based technology to optimize inservice inspection of nuclear power plants. The subcommittee is responsible for the content of ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The paper will first provide the historical background for the inspection program currently in Section XI. It will then describe the development of new technology through the ASME Center for Research and Technology Development program. Next, the work now going on in two of the groups under the Section XI committee will be described in detail. Each of these two efforts is directed toward the application of new risk-based inspection technology to nuclear piping systems. Finally, the directions of additional research and applications of the technology will be discussed. (author)

  13. Impact of ACI-ASME code on design and construction of nuclear containment structures

    International Nuclear Information System (INIS)

    Reedy, R.F.

    1978-01-01

    The effect of the ACI-ASME code for design and construction of concrete containment structures on the nuclear and concrete industries is examined. Topics covered include purpose of the code, general requirements, responsibilities and duties, design and construction specifications, quality assurance, inspection, the liner, and stamping

  14. Elastic-plastic stress analysis and ASME code evaluation of a bottomhead penetration in a reactor pressure vessel

    International Nuclear Information System (INIS)

    Ranganath, S.

    1979-01-01

    Nuclear pressure vessel components are designed to meet the requirements of Section III of the ASME Boiler and Pressure Vessel Code. Specifically, the design must satisfy the limits on stress range and fatigue usage prescribed in NB-3200, Section III ASME Code for the various design and operating conditions for the component. The Code requirements assure that the component does not experience gross yielding and that in general, elastic shakedown occurs following cyclic loading. When elastic stress analysis is performed this can be shown by meeting the limits in the Code on Primary and Primary plus Secondary (P+Q) stress intensities. However, when the P+Q limits cannot be met and elastic Shakedown cannot be demonstrated, plastic analysis may be performed to meet the requirements of the Code. This paper describes the elastic-plastic stress analysis of a Boiling Water Reactor Vessel bottom head in-core penetration and illustrates how plastic analysis can be used in ASME Code evaluations to show Code compliance. Details of the thermal analysis, elastic-plastic stress analysis and fatigue evaluation are presented and it is shown that the in-core penetration satisfies the code requirements. 6 refs

  15. CONAGT's place in ASME's centennial year

    International Nuclear Information System (INIS)

    Miller, W.H. Jr.

    1985-01-01

    A status report on ASME's Committee on Nuclear Air and Gas Treatment (CONAGT) is presented. This year ASME celebrates its centennial while CONAGT issues its first code sections covering fans, blowers, and refrigeration equipment. Significant code related CONAGT activities are covered as well as an explanation of CONAGT's place in the ASME organization

  16. Integrity evaluation for stud female threads on pressure vessel according to ASME code using FEM

    International Nuclear Information System (INIS)

    Kim, Moon Young; Chung, Nam Yong

    2003-01-01

    The extension of design life among power plants is increasingly becoming a world-wide trend. Kori no.1 unit in Korea is operating two cycle. It has two man-ways for tube inspection in a steam generator which is one of the important components in a nuclear power plant. Especially, stud bolts for man-way cover have damaged by disassembly and assembly several times and degradation for bolt materials for long term operation. It should be evaluated and compared by ASME code criteria for integrity evaluation. Integrity evaluation criteria which has been made by the manufacturer is not applied on the stud bolts of nuclear pressure vessels directly because it is controlled by the yield stress of ASME code. It can apply evaluation criteria through FEM analysis to damaged female threads and to evaluated safety for helical-coil method which is used according to code case-N-496-1. From analysis results, we found that it is the same results between stress intensity which got from FEM analysis on damaged female threads over 10% by manufacture integrity criteria and 2/3 yield strength criteria on ASME code. It was also confirmed that the helical-coil repair method would be safe

  17. Elastic creep-fatigue evaluation for ASME [American Society of Mechanical Engineers] code

    International Nuclear Information System (INIS)

    Severud, L.K.; Winkel, B.V.

    1987-02-01

    Reassessment of past ASME N-47 creep-fatigue rules have been under way by committee members. The new proposed elastic creep-fatigue methods are easier to apply than those previously in the code case. They also provide a wider range of practical application while still providing conservative assessments. It is expected that new N-47 code rules for elastic creep-fatigue evaluation will be adopted in the near future

  18. Modification of the ASME code z-factor for circumferential surface crack in nuclear ferritic pipings

    International Nuclear Information System (INIS)

    Choi, Young Hwan; Chung, Yon Ki; Koh, Wan Young; Lee, Joung Bae

    1996-01-01

    The purpose of this paper is to modify the ASME Code Z-Factor, which is used in the evaluation of circumferential surface crack in nuclear ferritic pipings. The ASME Code Z-Factor is a load multiplier to compensate plastic load with elasto-plastic load. The current ASME Code Z-Factor underestimates pipe maximum load. In this study, the original SC. TNP method is modified first because the original SC. TNP method has a problem that the maximum allowable load predicted from the original SC. TNP method is slightly higher than that measured from the experiment. Then the new Z-Factor is developed using the modified SC. TNP method. The desirability of both the modified SC. TNP method and the new Z-Factor is examined using the experimental results for the circumferential surface crack in pipings. The results show that (1) the modified SC. TNP method is good for predicting the circumferential surface crack behavior in pipings, and (2) the Z-Factor obtained from the modified SC. TNP method well predicts the behavior of circumferential surface crack in ferritic pipings. 30 refs., 13 figs., 4 tabs. (author)

  19. 46 CFR 54.01-2 - Adoption of division 1 of section VIII of the ASME Boiler and Pressure Vessel Code.

    Science.gov (United States)

    2010-10-01

    ... Boiler and Pressure Vessel Code. 54.01-2 Section 54.01-2 Shipping COAST GUARD, DEPARTMENT OF HOMELAND... division 1 of section VIII of the ASME Boiler and Pressure Vessel Code. (a) Pressure vessels shall be designed, constructed, and inspected in accordance with section VIII of the ASME Boiler and Pressure Vessel...

  20. 46 CFR 53.01-3 - Adoption of section IV of the ASME Boiler and Pressure Vessel Code.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Adoption of section IV of the ASME Boiler and Pressure...) MARINE ENGINEERING HEATING BOILERS General Requirements § 53.01-3 Adoption of section IV of the ASME Boiler and Pressure Vessel Code. (a) Heating boilers shall be designed, constructed, inspected, tested...

  1. 46 CFR 52.01-2 - Adoption of section I of the ASME Boiler and Pressure Vessel Code.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Adoption of section I of the ASME Boiler and Pressure...) MARINE ENGINEERING POWER BOILERS General Requirements § 52.01-2 Adoption of section I of the ASME Boiler and Pressure Vessel Code. (a) Main power boilers and auxiliary boilers shall be designed, constructed...

  2. Estimates of the burst reliability of thin-walled cylinders designed to meet the ASME Code allowables

    International Nuclear Information System (INIS)

    Stancampiano, P.A.; Zemanick, P.P.

    1976-01-01

    Pressure containment components in nuclear power plants are designed by the conventional deterministic safety factor approach to meet the requirements of the ASME Pressure Vessel Code, Section III. The inevitable variabilities and uncertainties associated with the design, manufacture, installation, and service processes suggest a probabilistic design approach may also be pertinent. Accordingly, the burst reliabilities of two thin-walled 304 SS cylindrical vessels such as might be employed in liquid metal plants are estimated. A large vessel fabricated from rolled plate per ASME SA-240 and a smaller pipe sized vessel also fabricated from rolled plate per ASME SA-358 are considered. The vessels are sized to just meet the allowable ASME Code primary membrance stresses at 800 0 F (427 0 C). The bursting probability that the operating pressure is greater than the burst strength of the cylinders is calculated using stress-strength interference theory by direct Monte Carlo simulation on a high speed digital computer. A sensitivity study is employed to identify those design parameters which have the greatest effect on the reliability. The effects of preservice quality assurance defect inspections on the reliability are also evaluated parametrically

  3. Design specifications for ASME B and PV Code Section III nuclear class 1 piping

    International Nuclear Information System (INIS)

    Richardson, J.A.

    1978-01-01

    ASME B and PV Code Section III code regulations for nuclear piping requires that a comprehensive Design Specification be developed for ensuring that the design and installation of the piping meets all code requirements. The intent of this paper is to describe the code requirements, discuss the implementation of these requirements in a typical Class 1 piping design specification, and to report on recent piping failures in operating light water nuclear power plants in the US. (author)

  4. Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles

    International Nuclear Information System (INIS)

    Nitzel, M.E.; Ware, A.G.; Morton, D.K.

    1996-01-01

    Fatigue analyses wre conducted on two reactor coolant system branch nozzles in an operating PWR designed to the B31.1 Code, for which no explicit fatigue analysis was required by the licensing basis. These analyses were performed as part of resolving issues connected with NRC's Fatigue Action Plan to determine if the cumulative usage factor (CUF) for these nozzles, using the 1992 ASME Code and representative PWR transients, were comparable to nozzles designed and analyzed to the ASME Code. Both NB-3200 and NB-3600 ASME Code methods were used. NB-3200 analyses included the development of finite element models for each nozzle. Although detailed thermal transients were not available for the plant analyzed, representative transients from similar PWRs were applied in each method. CUFs calculated using NB-3200 methods were significantly less than using NB-3600. The paper points out differences in analysis methods and highlights difficulties and unknowns in performing more detailed analyses to reduce conservative assumptions

  5. Procedures of ASME code case N-201 for KALIMER. Reactor internal structures

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Yoo, B.

    2001-02-01

    The main objective of this report is to describe the design procedure of ASME Boiler and Pressure Vessel Code, Code Case N-201-4, which is an elevated temperature structural design code of the Nuclear reactor internal structures, checking the criteria of stress limit, accumulated inelastic strain and deformation, creep-fatigue damage, and buckling limit. As one of examples, the creep-fatigue damage evaluations are carried out for the KALIMER reactor internal structures of baffle annulus. This report is expected to be very useful in evaluating the structural integrity of the liquid metal reactor operating under an elevated temperature

  6. The ASME section XI code, past, present, and future

    International Nuclear Information System (INIS)

    Anderson, W.F.; Bush, S.H.; Chockie, L.J.

    1982-01-01

    A little over a decade has passed since the first drafts of the Codes effecting the program of inservice inspections in the United States have been implemented and enforced in operating power plants. During the ensuing years, advantage has been taken of results of the application of the program of inspections and tests. In several instances, the Code has been revised to correct deficiencies, and additional rules have been added to accommodate additional systems and portions of the plant which were deemed to also be important to safety. Additional rules have now been published to recognize the liquid metal cooled reactor systems and the gas cooled reactor systems along with the water cooled reactor systems. While the past and the present can be stated with considerable certainty, opinions of the authors, each of whom is a member of the American Society of Mechanical Engineers (ASME) Code Committee, are advanced as to their plans which will reveal the direction the Code is projected to follow in the future. (author)

  7. Materials and design bases issues in ASME Code Case N-47

    International Nuclear Information System (INIS)

    Huddleston, R.L.; Swindeman, R.W.

    1993-04-01

    A preliminary evaluation of the design bases (principally ASME Code Case N-47) was conducted for design and operation of reactors at elevated temperatures where the time-dependent effects of creep, creep-fatigue, and creep ratcheting are significant. Areas where Code rules or regulatory guides may be lacking or inadequate to ensure the operation over the expected life cycles for the next-generation advanced high-temperature reactor systems, with designs to be certified by the US Nuclear Regulatory Commission, have been identified as unresolved issues. Twenty-two unresolved issues were identified and brief scoping plans developed for resolving these issues

  8. Comparative study of design of piping supports class 1, 2 and 3 considering german code KTA and ASME III - NF

    International Nuclear Information System (INIS)

    Faloppa, Altair A.; Fainer, Gerson; Mattar Neto, Miguel; Elias, Marcos V.

    2013-01-01

    The objective of this paper is developing a comparative study of the design criteria for class 1, 2, 3 piping supports considering the American Code ASME Section III - NF and the German Code KTA 3205.1 to the Primary Circuit, KTA 3205.2 to the others systems and KTA 3205.3 series-production standards supports of a PWR nuclear power plant. An additional purpose of the paper is a general analysis of the main design concepts of the American Code ASME Boiler and Pressure Vessel Code, Section III, Division 1 and German Nuclear Design Code KTA that was performed in order to aid the comparative study proposed. The relevance of this study is to show the differences between codes ASME and KTA since they were applied in the design of the Nuclear Power Plants Angra 1 and Angra 2, and to the design of Angra 3, which is at the moment under construction. It is also considered their use in the design of nuclear installations such as RMB - Reator MultiProposito Brasileiro and LABGENE - Laboratorio de Geracao Nucleoeletrica. (author)

  9. Prediction of surface cracks from thick-walled pressurized vessels with ASME code

    International Nuclear Information System (INIS)

    Thieme, W.

    1983-01-01

    The ASME-Code, Section XI, Appendix A 'Analysis of flow indications' is still non-mandatory for the pressure components of nuclear power plants. It is certainly difficult to take realistic account of the many factors influencing crack propagation while making life predictions. The accuracy of the US guideline is analysed, and its possible applications are roughly outlined. (orig./IHOE) [de

  10. Adoption of ASME Code Section XI for ISI to Research Reactors

    International Nuclear Information System (INIS)

    Tawfik, Y.E.; El-sesy, I.A.; Shaban, H.I.; Ibrahim, M.M.

    2002-01-01

    ETRR-2 (Second Egyptian thermal research reactor) is a multi-purpose, pool- type reactor with an open water surface and variable core arrangement. The core power is 22 MWth, cooled and moderated by light water and with beryllium reflectors. It contains plate- type fuel elements (MTR type, 19.7% enriched uranium) with aluminum clad. The ETRR-2 reactor consist of 57 systems and around 200 subsystems. These systems contain many mechanical components such as tanks, pipes, valves, pumps, heat exchangers, cooling tower, air compressors, and supports. In this present work, a trial was made to adopt the general requirements of ASME code, section XI to ETRR-2 research reactor. ASME (American Society of Mechanical Engineers) boiler and pressure vessel Code, section XI, provides requirements for in-service inspection (ISI) and in-service testing (IST) of components and systems, and repair/replacement activities in a nuclear power plant. Also, IAEA (International Atomic Energy Authority) has published some recommendations for ISI for research reactors similar to that rules and requirements specified in ASME. The complete ISI program requires several steps that have to be performed in sequence. These steps are described in many logic flow charts (LFC's). These logic flow charts include; the general LFC's for all steps required to complete ISI program, the LFC's for examination requirements, the LFC's for flaw evaluation modules, and the LFC's for acceptability of welds for class 1 components. This program includes, also, the inspection program for welded parts of the reactor components during its lifetime. This inspection program is applied for each system and subsystem of ETRR-2 reactor. It includes the examination area type, the component type, the part to be examined, the weld type, the examination method, the inspection program schedule, and the detailed figures of the welded components. (authors)

  11. Activated sludge models ASM1, ASM2, ASM2d and ASM3

    DEFF Research Database (Denmark)

    Henze, Mogens; Gujer, W.; Mino, T.

    This book has been produced to give a total overview of the Activated Sludge Model (ASM) family at the start of 2000 and to give the reader easy access to the different models in their original versions. It thus presents ASM1, ASM2, ASM2d and ASM3 together for the first time.Modelling of activated...... sludge processes has become a common part of the design and operation of wastewater treatment plants. Today models are being used in design, control, teaching and research.ContentsASM3: Introduction, Comparison of ASM1 and ASM3, ASM3: Definition of compounds in the model, ASM3: Definition of processes...... in the Model, ASM3: Stoichiometry, ASM3: Kinetics, Limitations of ASM3, Aspects of application of ASM3, ASM3C: A Carbon based model, Conclusion ASM 2d: Introduction, Conceptual Approach, ASM 2d, Typical Wastewater Characteristics and Kinetic and Stoichiometric Constants, Limitations, Conclusion ASM 2...

  12. Comparison of SKIFS 2004:1 and Tillsynshandbok PSA against the ASME PRA Standard and European requirements on PSA

    International Nuclear Information System (INIS)

    Hellstroem, Per

    2005-04-01

    Requirements on PSA for risk informed applications are expressed in different international documents. The ASME PRA standard published in spring 2002 is one such document, PSA requirements are also expressed in the European Utility Requirements (EUR) for new reactors. The Swedish PSA requirements are provided in the Swedish regulators (SKI) statutes SKIFS 2004:1. SKI also has a review handbook for PSA activities (SKI report 2003:48). The review handbook is a support during review of the utilities PSA activities and the PSAs themselves. The review handbook expresses SKIs expectations by providing so called important aspects for both the PSA work and the PSAs, A comparison of SKIFS requirements and the important aspects in the Review handbook, on one side, and the requirements on PSA in EUR and ASME on the other side, is presented. The comparison shows a large difference in the level of detail in the different documents, where ASME is most detailed and specific. This is expected since the SKI review handbook not is a 'PSA guide' in the same way as the ASME PRA standard. A direct comparison of the ASME PRA standard requirements with the important aspects in the review handbook cannot answer the question which ASME capacity level that is achieved by a PSA meeting all important aspects. The conclusion is that it is not likely to achieve capacity level 2 and 3, since very few ASME level 3 attributes are explicitly expressed as important aspects, though many are expressed in general terms. The review handbook important aspects that are most similar to the ASME capacity level 1 attributes are initiating events, sequence analysis, and system analysis while less similarity is found for analysis of operator actions data analysis, quantification and containment analysis (level 2). Less similarity is found for capacity level 2 and 3. However, the number of additional ASME attributes on capacity level 2 and 3 are few. There are also important aspects in the review handbook that

  13. Proceedings of the European Symposium on Pressure Equipment - ESOPE 2004

    International Nuclear Information System (INIS)

    2004-01-01

    The symposium on Pressure Equipment Technology, organised every three years by the AFIAP (Association Francaise des Ingenieurs en Appareils a Pression), for the second time is organised at the European level. It is the 'European Symposium on Pressure Equipment, ESOPE 2004'. This symposium is placed under the patronage of the Minister of Industry. The central theme of ESOPE 2001 has been the European Directives for Fixed Equipment (PED) and for Transportable Equipment (TPED). ESOPE 2004 will be a state on the application of these Directives after 3 years of use. The first plenary session will made the comparison of some National codes with EN13445 standard and of the evolution of the Asme code. But the principal theme of the second plenary session and the panel, where European experts will answer to your questions, will be on 'Pressure equipment life management'. It therefore seems important to incorporate this subject into the agenda of this symposium in order to allow widespread dialogue between the industrial members concerned. Our association, AFIAP, has the advantage of regrouping all the industrial partners concerned, from the end user and the administrative body responsible for equipment safety, to the pressure equipment fabricator and his materials suppliers, also including those bodies responsible for design, inspection and certification. To improve availability of equipment and reduce production costs the most efficient way is the development of technology. It is essential to improve competitiveness of European companies. Research is necessary, but the results must be available to everyone, including small and medium-sized industries. ESOPE 2004 has 3 technical sessions in parallel, which will be followed, by many fruitful exchanges of experience: - design/materials - fabrication/welding/inspection - fitness for service. You will find on a CD-Rom all the contributions which have been presented. (authors)

  14. Application of ASME code AG-1 to YGN 3 ampersand 4 plants, South Korea

    International Nuclear Information System (INIS)

    Kim, Y.K.; Porco, R.D.; York, Y.D.

    1993-01-01

    Yonggwang Nuclear Power Plant Units 3 ampersand 4 are located on the southwestern coast of South Korea on the Yellow Sea. The plant is owned by Korea Electric Power Corp. (KEPCO), with the engineering being performed by Korea Power Engineering Co., Inc. (KOPEC) and Sargent and Lundy under a technology transfer agreement. The plants are both 950 Megawatt (electric) pressurized water reactors of US design. Under contract to KEPCO, Korea Heavy Industries and Construction Co., Ltd. and Ellis and Watts, Division of Dynamics Corporation of America, Batavia, Ohio, supplied major components to the YGN plants in compliance to ASME AG-1. These components included safety related Air Cleaning Units, Reactor containment Fan Cooler Units, Air Handling Units, Cubicle Coolers, Duct Electric Heaters, and fans. This paper details the extent of applicability of ASME Code AG-1 to the specific equipment, description of the equipment, conformance, testing, and design required. The paper also discusses the problems encountered in implementing ASME AG-1, working around Code sections that were not complete at contract inception, conflicts in project documents and related problems. Also discussed are the logistics problems, material availability, and quality assurance aspects complicating the applications of ASME AG-1, due to the required Korean content for some components. Based on successfully supplying the equipment referenced above, it has been concluded that AG-1 is a working document and can be successfully implemented. It provides the requirements necessary for performance, design, construction, acceptance testing, and quality assurance of equipment used as components in nuclear air and gas treatment systems in nuclear facilities. The paper also addresses lessons learned and aspects of mixing US design and US built components in Korean built assemblies

  15. FY16 ASME High Temperature Code Activities

    Energy Technology Data Exchange (ETDEWEB)

    Swindeman, M. J. [Chromtech Inc., Oak Ridge, TN (United States); Jetter, R. I. [R. I Jetter Consulting, Pebble Beach, CA (United States); Sham, T. -L. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-01

    One of the objectives of the ASME high temperature Code activities is to develop and validate both improvements and the basic features of Section III, Division 5, Subsection HB, Subpart B (HBB). The overall scope of this task is to develop a computer program to be used to assess whether or not a specific component under specified loading conditions will satisfy the elevated temperature design requirements for Class A components in Section III, Division 5, Subsection HB, Subpart B (HBB). There are many features and alternative paths of varying complexity in HBB. The initial focus of this task is a basic path through the various options for a single reference material, 316H stainless steel. However, the program will be structured for eventual incorporation all the features and permitted materials of HBB. Since this task has recently been initiated, this report focuses on the description of the initial path forward and an overall description of the approach to computer program development.

  16. A user's perspective on the merits and shortcomings of ASME Section III

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1994-01-01

    There are several aspects of Section III which when compared to process industry codes (ASME VIII, ASME B31.3, API, etc.) have proven to be a significant improvement in engineering practice. There are, however, other aspects of ASME III which have added to costs without clear benefits in safety or reliability. The authors present a user's perspective on some of the relative merits and shortcomings of the nuclear codes (ASME III and XI) compared to the process industry codes (such as ASME VIII, B31.3 and API)

  17. Draft ASME code case on ductile cast iron for transport packaging

    International Nuclear Information System (INIS)

    Saegusa, T.; Arai, T.; Hirose, M.; Kobayashi, T.; Tezuka, Y.; Urabe, N.; Hueggenberg, R.

    2004-01-01

    The current Rules for Construction of ''Containment Systems for Storage and Transport Packagings of Spent Nuclear Fuel and High Level Radioactive Material and Waste'' of Division 3 in Section III of ASME Code (2001 Edition) does not include ductile cast iron in its list of materials permitted for use. The Rules specify required fracture toughness values of ferritic steel material for nominal wall thickness 5/8 to 12 inches (16 to 305 mm). New rule for ductile cast iron for transport packaging of which wall thickness is greater than 12 inches (305mm) is required

  18. Development and application of proposed ASME Section XI Code changes for risk-based inspection of piping

    International Nuclear Information System (INIS)

    West, R.A.

    1996-01-01

    This synopsis has been written to describe a perspective on the development and application of ASME Section XI Code changes for risk-based inspection of piping. The content is specifically related to the use of risk-based technology for Inservice Inspection (ISI) of piping and efforts made to support the ASME Research/Westinghouse Owners Group/Millstone Unit 3 approach for use of this technology. The opinions contained herein may or may not reflect those of the ASME Codes and Standards Committees responsible for these activities. In order to take such a detailed technical subject and put it into an understandable format, the author has chosen to provide an analogy to simplify what is actually taking place. Risk-based technology in the ISI of piping can be likened to the process of making and using specifically ground prescription glasses to allow for better vision. It provides a process to develop and use these uniquely ground glasses that will dynamically focus on all the locations and obstacles within a plant's piping systems that could cause that plant to trip and fall; more importantly it identifies the locations where the fall could possibly hurt someone else. In this way, Nuclear Safety is being addressed

  19. Developments on ASME Code Cases to Risk-Informed Repair/Replacement Activities in Support of Risk-Informed Regulation Initiatives

    International Nuclear Information System (INIS)

    Balkey, Kenneth R.; Holston, William C.

    2002-01-01

    ASME Code Case N-658, 'Risk-Informed Safety Classification for Use in Risk-Informed Repair/Replacement Activities' and Code Case N-660, 'Alternative Repair/Replacement Requirements For Items Classified In Accordance With Risk-Informed Processes' are being completed to expand the breadth of risk-informed requirements for pressure-retaining items. This initiative, which is built from prior ASME Section XI risk-informed inservice inspection developments over the past decade, has been undertaken in conjunction with U.S. risk-informed regulation efforts. The U.S. Nuclear Regulatory Commission (NRC) is working with the industry on risk informing Title 10 Code of Federal Regulations Part 50 (10CFR50). The Nuclear Regulatory Commission's basic proposal is to allow modification of some of the special treatment requirements of 10CFR50. Their effort is proceeding via an Advanced Notice of Public Rulemaking, March 3, 2000, and an announcement of Availability of Draft Rule Wording, November 29, 2001, to add 10 CFR 50.69, 'Risk-Informed Treatment of Structures, Systems and Components'. A parallel task by the Nuclear Energy Institute (NEI) to develop a guideline on how to implement the results of the rulemaking is also well underway via NEI 00-04 (Draft Revision B), 'Option 2 Implementation Guideline', May 2001. This paper summarizes the content and status of approval of the proposed ASME Code Cases, including how they relate to the above NRC and NEI efforts. Some initial results from trial application of the Code Cases will also be cited. (authors)

  20. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    International Nuclear Information System (INIS)

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the open-quotes constructionclose quotes of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc

  1. Meeting the difficulties of an ASME calibration for pipe welds

    Energy Technology Data Exchange (ETDEWEB)

    Ginzel, E., E-mail: eginzel@mri.on.ca [Materials Research Inst., Waterloo, Ontario (Canada); Ginzel, R.; Buchholz, J., E-mail: rginzel@eclipsescientific.com [Eclipse Scientific, Waterloo, Ontario (Canada)

    2013-11-15

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel code Section V deals with Non-Destructive Testing (NDT). In North America the use of ASME Sec. V is not always limited to just ASME regulated projects. Even such seemingly unrelated Standards as CSA Z662 (the Canadian construction standard for Oil and Gas Pipeline Systems) references this document for some aspects of the NDT. ASME has several codes that are dedicated to piping welds, for example ASME 31.1, 31.3 and 31.8. All of them reference back to ASME Section V Article 4 for the accepted techniques to use when UT is the examination option, but sometimes ASME is not very helpful. As they try to leave options open in one area they close the doors in others, or so it seems when reading the clauses as mandatory where you see the word 'shall'. This paper will attempt to layout the issues with pipe weld inspections as per Article 4, 2011 edition. Like all other codes and standards, ASME is a regulated standard that is regularly reviewed and updated, and one must be careful to reference the year of the edition being used. For the purposes of this paper we have used the 2010/11 edition. (author)

  2. Meeting the difficulties of an ASME calibration for pipe welds

    International Nuclear Information System (INIS)

    Ginzel, E.; Ginzel, R.; Buchholz, J.

    2013-01-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel code Section V deals with Non-Destructive Testing (NDT). In North America the use of ASME Sec. V is not always limited to just ASME regulated projects. Even such seemingly unrelated Standards as CSA Z662 (the Canadian construction standard for Oil and Gas Pipeline Systems) references this document for some aspects of the NDT. ASME has several codes that are dedicated to piping welds, for example ASME 31.1, 31.3 and 31.8. All of them reference back to ASME Section V Article 4 for the accepted techniques to use when UT is the examination option, but sometimes ASME is not very helpful. As they try to leave options open in one area they close the doors in others, or so it seems when reading the clauses as mandatory where you see the word 'shall'. This paper will attempt to layout the issues with pipe weld inspections as per Article 4, 2011 edition. Like all other codes and standards, ASME is a regulated standard that is regularly reviewed and updated, and one must be careful to reference the year of the edition being used. For the purposes of this paper we have used the 2010/11 edition. (author)

  3. Update on ASME rules for spent nuclear fuel and high level radioactive material and waste storage containments

    International Nuclear Information System (INIS)

    Ralph S. Hill III; Foster, G.M.

    2005-01-01

    In 2004, a new Code Case, N-717, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) was published. The Code Case provides rules for construction of containments used for storage of spent nuclear fuel and high level radioactive material and waste. The Code Case has been incorporated into Section III of the Code as Division 3, Subsection WC, Class SC Storage Containments, and will be published in the 2005 Addenda. This paper provides an informative background and insight for these rules to provide Owners, regulators, designers, and fabricators with a more comprehensive understanding of the technical basis for these rules. (authors)

  4. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the {open_quotes}construction{close_quotes} of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc.

  5. Description of comprehensive pump test change to ASME OM code, subsection ISTB

    International Nuclear Information System (INIS)

    Hartley, R.S.

    1994-01-01

    The American Society of Mechanical Engineers (ASME) Operations and Maintenance (OM) Main Committee and Board on Nuclear Codes and Standards (BNCS) recently approved changes to ASME OM Code-1990, Subsection ISTB, Inservice Testing of Pumps in Light-Water Reactor Power Plants. The changes will be included in the 1994 addenda to ISTB. The changes, designated as the comprehensive pump test, incorporate a new, improved philosophy for testing safety-related pumps in nuclear power plants. An important philosophical difference between the open-quotes old codeclose quotes inservice testing (IST) requirements and these changes is that the changes concentrate on less frequent, more meaningful testing while minimizing damaging and uninformative low-flow testing. The comprehensive pump test change establishes a more involved biannual test for all pumps and significantly reduces the rigor of the quarterly test for standby pumps. The increased rigor and cost of the biannual comprehensive tests are offset by the reduced cost of testing and potential damage to the standby pumps, which comprise a large portion of the safety-related pumps at most plants. This paper provides background on the pump testing requirements, discusses potential industry benefits of the change, describes the development of the comprehensive pump test, and gives examples and reasons for many of the specific changes. This paper also describes additional changes to ISTB that will be included in the 1994 addenda that are associated with, but not part of, the comprehensive pump test

  6. Technical Review on Fitness-for-Service for Buried Pipe by ASME Code Case N-806

    International Nuclear Information System (INIS)

    Park, Sang Kyu; Lee, Yo Seop; So, Il Su; Lim, Bu Taek

    2012-01-01

    Fitness-for-Service is a useful technology to determine replacement timing, next inspection timing or in-service when nuclear power plant's buried pipes are damaged. If is possible for buried pipes to be aged by material loss, cracks and occlusion as operating time goes by. Therefore Fitness-for-Service technology for buried pipe is useful for plant industry to perform replacement and repair. Fitness-for-Service for buried pipe is studied in terms of existing code and standard for Fitness-for-Service and a current developing code case. Fitness-for-Service for buried pipe was performed according to Code Case N-806 developed by ASME (American Society of Mechanical Engineers)

  7. Nuclear component design ontology building based on ASME codes

    International Nuclear Information System (INIS)

    Bao Shiyi; Zhou Yu; He Shuyan

    2005-01-01

    The adoption of ontology analysis in the study of concept knowledge acquisition and representation for the nuclear component design process based on computer-supported cooperative work (CSCW) makes it possible to share and reuse numerous concept knowledge of multi-disciplinary domains. A practical ontology building method is accordingly proposed based on Protege knowledge model in combination with both top-down and bottom-up approaches together with Formal Concept Analysis (FCA). FCA exhibits its advantages in the way it helps establish and improve taxonomic hierarchy of concepts and resolve concept conflict occurred in modeling multi-disciplinary domains. With Protege-3.0 as the ontology building tool, a nuclear component design ontology based ASME codes is developed by utilizing the ontology building method. The ontology serves as the basis to realize concept knowledge sharing and reusing of nuclear component design. (authors)

  8. Nupack, the new ASME code for radioactive material transportation packaging containments

    International Nuclear Information System (INIS)

    Turula, P.

    1998-01-01

    The American Society of Mechanical Engineers (ASME) has added a new division to the nuclear construction section of its Boiler and Pressure Vessel Code (B and PVC). This Division, commonly referred to as Nupack, has been written to provide a consistent set of technical requirements for containment vessels of transportation packagings for high-level radioactive materials. This paper provides an introduction to Nupack, discusses some of its technical provisions, and describes how it can be used for the design and construction of packaging components. Nupack's general provisions and design requirements are emphasized, while treatment of materials, fabrication and inspection is left for another paper

  9. Evaluation of flaws in ferritic piping: ASME Code Appendix J, Deformation Plasticity Failure Assessment Diagram (DPFAD)

    International Nuclear Information System (INIS)

    Bloom, J.M.

    1991-08-01

    This report summarizes the methods and bases used by an ASME Code procedure for the evaluation of flaws in ferritic piping. The procedure is currently under consideration by the ASME Boiler and Pressure Vessel Code Committee of Section 11. The procedure was initially proposed in 1985 for the evaluation of the acceptability of flaws detected in piping during in-service inspection for certain materials, identified in Article IWB-3640 of the ASME Boiler and Pressure Vessel Code Section 11 ''Rules for In-service Inspection of Nuclear Power Plant Components.'' for which the fracture toughness is not sufficiently high to justify acceptance based solely on the plastic limit load evaluation methodology of Appendix C and IWB-3641. The procedure, referred to as Appendix J, originally included two approaches: a J-integral based tearing instability (J-T) analysis and the deformation plasticity failure assessment diagram (DPFAD) methodology. In Appendix J, a general DPFAD approach was simplified for application to part-through wall flows in ferritic piping through the use of a single DPFAD curve for circumferential flaws. Axial flaws are handled using two DPFAD curves where the ratio of flaw depth to wall thickness is used to determine the appropriate DPFAD curve. Flaws are evaluated in Appendix J by comparing the actual pipe applied stress with the allowable stress with the appropriate safety factors for the flaw size at the end of the evaluation period. Assessment points for circumferential and axial flaws are plotted on the appropriate failure assessment diagram. In addition, this report summarizes the experimental test predictions of the results of the Battelle Columbus Laboratory experiments, the Eiber experiments, and the JAERI tests using the Appendix J DPFAD methodology. Lastly, this report also provides guidelines for handling residual stresses in the evaluation procedure. 22 refs., 13 figs., 5 tabs

  10. Risk-informed technology developments for nuclear power plants within the ASME in 2000-2001

    International Nuclear Information System (INIS)

    Wesley Rowley, C.; Balkey, K.R.

    2001-01-01

    The purpose of this paper is to provide information on developments within the ASME to support risk-informing NRC regulations for nuclear power plants. This paper builds on a publication at ICONE-8 that discussed ASME risk-informed nuclear power plant initiatives, both in Research and in Codes and Standards, particularly those related to risk-informing Part 50 of the 10 CFR (Code of federal regulations). During the past year, the ASME BNCS formed a Task Force to focus the Society's efforts to support risk-informing 10 CFR Part 50. Key efforts underway that are guided by the task force include finalizing the ASME PRA (probability risk assessment) Standard, developing a Code Case to risk-inform the repair, replacement, and modification activities for ASME components, and developing a Code Case to risk-inform the safety classification of pressure boundary components. Several other initiatives are also under investigation such as introducing risk insights into other ASME nuclear codes and standards supported by appropriate research and technical basis information. Supplementary information will also be provided to update an initial high level plan of ASME risk-informed initiatives for nuclear power plants that was presented at ICONE-8, including plans to communicate these risk-informed technology developments to the public. The authors included and acknowledged contributions from several other cognizant members of the ASME BNCS (board on nuclear codes standards) Task Group on RIP50 in the paper. (authors)

  11. ASME code and ratcheting in piping components. Final technical report

    International Nuclear Information System (INIS)

    Hassan, T.; Matzen, V.C.

    1999-01-01

    The main objective of this research is to develop an analysis program which can accurately simulate ratcheting in piping components subjected to seismic or other cyclic loads. Ratcheting is defined as the accumulation of deformation in structures and materials with cycles. This phenomenon has been demonstrated to cause failure to piping components (known as ratcheting-fatigue failure) and is yet to be understood clearly. The design and analysis methods in the ASME Boiler and Pressure Vessel Code for ratcheting of piping components are not well accepted by the practicing engineering community. This research project attempts to understand the ratcheting-fatigue failure mechanisms and improve analysis methods for ratcheting predictions. In the first step a state-of-the-art testing facility is developed for quasi-static cyclic and seismic testing of straight and elbow piping components. A systematic testing program to study ratcheting is developed. Some tests have already been performed and the rest will be completed by summer'99. Significant progress has been made in the area of constitutive modeling. A number of sophisticated constitutive models have been evaluated in terms of their simulations for a broad class of ratcheting responses. From the knowledge gained from this evaluation study two improved models are developed. These models are demonstrated to have promise in simulating ratcheting responses in piping components. Hence, implementation of these improved models in widely used finite element programs, ANSYS and/or ABAQUS, is in progress. Upon achieving improved finite element programs for simulation of ratcheting, the ASME Code provisions for ratcheting of piping components will be reviewed and more rational methods will be suggested. Also, simplified analysis methods will be developed for operability studies of piping components and systems. Some of the future works will be performed under the auspices of the Center for Nuclear Power Plant Structures

  12. Progress toward NuPack, the ASME code for Type B containments

    International Nuclear Information System (INIS)

    Turula, P.

    1995-01-01

    This paper presented a brief status report on the development of an ASME Code Division for nuclear packaging and discussed some of the more interesting policy decisions as to what is and is not covered in terms of analytical methods, criteria, scope, and other aspects. The process of the development of this Division has been very slow and inconsistent. There were many participants with many diverse interests. The Division 3 rules are close to being ready to be issued. They are a compromise between many needs and the result is certainly not perfect. Opportunities for fine tuning and expanding this document will present themselves after it is issued as future needs become clear

  13. Application of the ASME code in the design of the GA-4 and GA-9 casks

    International Nuclear Information System (INIS)

    Mings, W.J.; Koploy, M.A.

    1992-01-01

    General Atomics (GA) is developing two spent fuel shipping casks for transport by legal weight truck (LWT). The casks are designed to the loading, environmental conditions and safety requirements defined in Title 10 of the Code of Federal Regulations, Part 71 (10CFR71). To ensure that all components of the cask meet the 10CFR71 rules, GA established structural design criteria for each component based on NRC Regulatory Guides and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This paper discusses the criteria used for different cask components, how they were applied and the conservatism and safety margins built into the criteria and assumption

  14. Comparison of elevated temperature design codes of ASME Subsection NH and RCC-MRx

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyeong-Yeon, E-mail: hylee@kaeri.re.kr

    2016-11-15

    Highlights: • Comparison of elevated temperature design (ETD) codes was made. • Material properties and evaluation procedures were compared. • Two heat-resistant materials of Grade 91 steel and austenitic stainless steel 316 are the target materials in the present study. • Application of the ETD codes to Generation IV reactor components and a comparison of the conservatism was conducted. - Abstract: The elevated temperature design (ETD) codes are used for the design evaluation of Generation IV (Gen IV) reactor systems such as sodium-cooled fast reactor (SFR), lead-cooled fast reactor (LFR), and very high temperature reactor (VHTR). In the present study, ETD code comparisons were made in terms of the material properties and design evaluation procedures for the recent versions of the two major ETD codes, ASME Section III Subsection NH and RCC-MRx. Conservatism in the design evaluation procedures was quantified and compared based on the evaluation results for SFR components as per the two ETD codes. The target materials are austenitic stainless steel 316 and Mod.9Cr-1Mo steel, which are the major two materials in a Gen IV SFR. The differences in the design evaluation procedures as well as the material properties in the two ETD codes are highlighted.

  15. Appropriate nominal stresses for use with ASME Code pressure-loading stress indices for nozzles

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.

    1976-06-01

    This program is part of a cooperative effort with industry to develop and verify analytical methods for assessing the safety of nuclear pressure-vessel and piping-system design. The study of nominal stresses and stress indices described is part of a continuing study of design rules for nozzles in pressure vessels being coordinated by the PVRC Subcommittee on Reinforced Openings and External Loadings. Results from these studies are used by appropriate ASME Code groups in drafting new and improved design rules

  16. Development of the present reference fracture toughness curves in the ASME nuclear code

    International Nuclear Information System (INIS)

    Yukawa, S.; Merkle, J.G.

    1984-01-01

    Since the early 1970's, the Sections of the ASME Boiler and Pressure Vessel Code concerned with nuclear power plant components have included fracture mechanics procedures to analyze the effects of postulated or detected flaws. These procedures are contained in Appendix G of Section III and in Appendix A of Section XI of the Code. Specifically, Appendix G procedures are concerned with designing for protection against nonductile failures while Appendix A procedures are for evaluating the disposition of flaws detected during in-service inspection. An important element of the procedures is the inclusion of recommended material fracture toughness values. This paper describes the origin and development of these recommended fracture toughness values. Since these values appear in the Code in a graphical format, the values are often referred to as reference toughness curves. In the context of Code terminology, reference toughness means the allowable values of fracture toughness for the materials of concern that can be used in conjunction with the analytical procedures of Appendices G and A. The paper discusses the basis and rationale underlying the original formulation of these reference toughness curves and the modifications incorporated into them in the course of their adoption into the Code

  17. Application procedures and analysis examples of the SIE ASME-NH program

    International Nuclear Information System (INIS)

    Kim, Seok Hoon; Koo, G. H.; Kim, J. B.

    2010-12-01

    In this report, the design rule of the ASME-NH Code was briefly summarized and the application procedures of SIE ASME-NH program were analysed, the analysis examples were described. The SIE ASME-NH program was developed according to the ASME Code Section III Subsection NH rules to perform the primary stress limits, the accumulated inelastic strain limits and the creep fatigue damage evaluations in the structural design of nuclear power plants operating with high temperatures over creep temperature at normal operating conditions. In the analysis examples, the benchmark problem for the high temperature reactor vessel which was discussed in the SIE ASME-NH user's seminar was described. Also, the preliminary structural analysis of an Advanced Burner Test Reactor internal structure was described. Considering the load combinations of the various cycle types submitted from significant operating conditions, the integrity of a reactor internal structure was reviewed according to the stress and strain limits of the ASME-NH rules and the analysis and evaluation results were summarized

  18. Nupack, the new Asme code for radioactive material transportation packaging containments

    International Nuclear Information System (INIS)

    Turula, P.

    1998-01-01

    The American Society of Mechanical Engineers (ASME) has added a new division to the nuclear construction section of its Boiler and Pressure Vessel Code (B and PVC). This Division, commonly referred to as 'Nupack', has been written to provide a consistent set of technical requirements for containment vessels of transportation packagings for high-level radioactive materials. This paper provides an introduction to Nupack, discusses some of its technical provisions, and describes how it can be used the design and construction of packaging components. Nupack's general provisions and design requirements are emphasized, while treatment of materials, fabrication and inspection is left for another paper. Participation in the Nupack development work described in this paper was supported by the U.S. Department of Energy. (authors)

  19. Technical basis for the extension of ASME Code Case N-494 for assessment of austenitic piping

    International Nuclear Information System (INIS)

    Bloom, J.M.

    1995-01-01

    In 1990, the ASME Boiler and Pressure Vessel Code for Nuclear Components approved Code Case N-494 as an alternative procedure for evaluating laws in Light Water Reactor alterative procedure for evaluating flaws in Light Water Reactor (LWR) ferritic piping. The approach is an alternative to Appendix H of the ASME Code and alloys the user to remove some unnecessary conservatism in the existing procedure by allowing the use of pipe specific material properties. The Code Case is an implementation of the methodology of the Deformation Plasticity Failure Assessment diagram (DPFAD). The key ingredient in the application of DPFAD is that the material stress-strain curve must be in the format of a simple power law hardening stress-strain curve such as the Ramberg-Osgood (R-O) model. Ferritic materials can be accurately fit by the R-O model and, therefore, it was natural to use the DPFAD methodology for the assessment of LWR ferritic piping. An extension of Code Case N-494 to austenitic piping required a modification of the existing DPFAD methodology. The Code Case N-494 approach was revised using the PWFAD procedure in the same manner as in the development of the original N-494 approach for ferritic materials. A lower bound stress-strain curve was used to generate a PWFAD curve for the geometry of a part-through wall circumferential flaw in a cylinder under tension. Earlier work demonstrated that a cylinder under axial tension with a 50% flaw depth, 90 degrees in circumference, and radius to thickness of 10, produced a lower bound FAD curve. Validation of the new proposed Code Case procedure for austenitic piping was performed using actual pipe test data. Using the lower bound PWFAD curve, pipe test results were conservatively predicted. The resultant development of ht PWFAD curve for austenitic piping led to a revision of Code Case N-494 to include a procedure for assessment of flaws in austenitic piping

  20. Evaluation of ASME code flaw analysis procedure using the influence function method for application to PWR primary piping

    International Nuclear Information System (INIS)

    Hong, S.Y.; Yeater, M.L.

    1985-01-01

    This paper discusses stress intensity factor calculations and fatigue analysis for a PWR primary coolant piping system. The influence function method is applied to evaluate ASME Code Section XI Appendix A ''analysis of flaw indication'' for the application to a PWR primary piping. Results of the analysis are discussed in detail. (orig.)

  1. ASME Section XI trends in developing nuclear codes and standards

    International Nuclear Information System (INIS)

    Hedden, O.F.

    1995-01-01

    When the author began working on nuclear power many years ago, he knew that perfection was the only acceptable technical standard. Unfortunately, this became an obsession with perfection that has had unfavorable consequences in some of the non-technical areas of work in ASME nuclear power Codes and Standards. However, the economic problems of the nuclear power industry now demand a more pragmatic approach if the industry is to continue. Not only does each item considered for action need to be evaluated to criteria that may in some cases be less than perfection, but one needs to consider whether it contributes tangibly to either safety or to reduction in technical or administrative burden. These should be the governing, criteria. The introduction of risk-based inspection methodologies will certainly be an important element in doing this successfully. One needs to consider these criteria collectively, as one discusses each item at the committee level, and individually, as one votes on each item. In the past, the author has been concerned that the industry was not acting quickly enough in taking advantage of opportunities offered by the Code to increase safety or to reduce cost. While he still has some concern, he thinks communication channels have been greatly improved. Now he is becoming more concerned with both the collective and individual actions that delay beneficial changes. The second part of the author's talk has to do with the relevance of the code committees in the nuclear power industry regulatory process

  2. Twenty years of fracture mechanics and flaw evaluation applications in the ASME Nuclear Code

    International Nuclear Information System (INIS)

    Riccardella, P.C.

    1991-01-01

    The paper presents a retrospective on the development and applications of fracture mechanics-based toughness requirements and flaw evaluation methodology in Sections III and XI of the ASME Code. Section III developments range from the rules and requirements for thick section Class 1 pressure vessels to thinner section components in other Classes. Section XI applications include flaw acceptance standards and evaluation methodology for various components ranging from pressure vessels to thins section piping of carbon and austenitic steels. The experience gained in operating plant applications of these rules and procedures are also discussed

  3. ASME section XI: rules for inservice inspection of nuclear power plants -an introspection

    Energy Technology Data Exchange (ETDEWEB)

    John, P K; Anto, Y; Mungikar, C P; Wagh, P M [Nuclear Power Corporation of India Ltd., Tarapur (India). Tarapur Atomic Power Station

    1994-12-31

    Section XI of the ASME BPV code is addressed to the examination, test and inspection requirements of the components of nuclear power plants (NPPs). Since its inception in 1970, this code section has undergone vast changes -probably the most among other ASME BPV code sections. Section XI is full fledged and lays down requirements with regard to all preservice inspections, inservice inspection, repair and replacement of components, tests of system etc. Tarapur Atomic Power Station (TAPS) has the distinction of being one of the earliest BWR type NPPs in the world that has an inservice inspection programme organised in line with the ASME section XI requirements. This paper summarises the experiences gained from time to time using this code section and a few suggestions to prospective users. An effort is also made to explain the philosophy of inservice inspection from ASME section XI point of view. 3 refs.

  4. ASME section XI: rules for inservice inspection of nuclear power plants -an introspection

    International Nuclear Information System (INIS)

    John, P.K.; Anto, Y.; Mungikar, C.P.; Wagh, P.M.

    1994-01-01

    Section XI of the ASME BPV code is addressed to the examination, test and inspection requirements of the components of nuclear power plants (NPPs). Since its inception in 1970, this code section has undergone vast changes -probably the most among other ASME BPV code sections. Section XI is full fledged and lays down requirements with regard to all preservice inspections, inservice inspection, repair and replacement of components, tests of system etc. Tarapur Atomic Power Station (TAPS) has the distinction of being one of the earliest BWR type NPPs in the world that has an inservice inspection programme organised in line with the ASME section XI requirements. This paper summarises the experiences gained from time to time using this code section and a few suggestions to prospective users. An effort is also made to explain the philosophy of inservice inspection from ASME section XI point of view. 3 refs

  5. News from the Library: A new key reference work for the engineer: ASME's Boiler and Pressure Vessel Code at the CERN Library

    CERN Multimedia

    CERN Library

    2011-01-01

    The Library is aiming at offering a range of constantly updated reference books, to cover all areas of CERN activity. A recent addition to our collections strengthens our offer in the Engineering field.   The CERN Library now holds a copy of the complete ASME Boiler and Pressure Vessel Code, 2010 edition. This code establishes rules of safety governing the design, fabrication, and inspection of boilers and pressure vessels, and nuclear power plant components during construction. This document is considered worldwide as a reference for mechanical design and is therefore important for the CERN community. The Code published by ASME (American Society of Mechanical Engineers) is kept current by the Boiler and Pressure Committee, a volunteer group of more than 950 engineers worldwide. The Committee meets regularly to consider requests for interpretations, revision, and to develop new rules. The CERN Library receives updates and includes them in the volumes until the next edition, which is expected to ...

  6. Review of ASME-NH Design Materials for Creep-Fatigue

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Kim, Jong Bum

    2010-01-01

    To review and recommend the candidate design materials for the Sodium-Cooled Fast Reactor, the material sensitivity evaluations by the comparison of design data between the ASME-NH materials were performed by using the SIE ASME-NH computer program implementing the material database of the ASME-NH. The design material data provided by the ASME-NH code are the elastic modulus and yield Strength, Time-Independent Allowable Stress Intensity value, time-dependent allowable stress intensity value, expected minimum stress-to rupture value, stress rupture Factors for weldment, isochronous stress-strain curves, and design fatigue curves. Among these, the data related with the creep-fatigue evaluation are investigated in this study

  7. An example of a component replacement when applying ASME N509 and ASME N510 to older ventilation systems

    International Nuclear Information System (INIS)

    Arndt, T.E.

    1994-06-01

    This paper presents an example of a component replacement (electric heater) when installed in an older ventilation system that was constructed before the issuance of ASME N509 and N510. Many of the existing ventilation systems at the Hanford Site were designed, fabricated, and installed before the issuance of ASME N509 and N510. Requiring the application of these codes to existing ventilation systems presents challenges to the engineer when design changes are needed. Although it may seem that the application of ASME N509 or N510 may be a hindrance at times, this does not need to occur. Proper preparation at the start of project or design modifications can minimize frustration to the engineer when it is judged that portions of ASME N509 and N510 do not apply in a particular application

  8. Rethinking ASME III seismic analysis for piping operability evaluations

    International Nuclear Information System (INIS)

    Adams, T.M.; Stevenson, J.D.

    1994-01-01

    It has been recognized since the mid 1980's that there are very large seismic margins to failure for nuclear piping systems when designed using current industry practice, design criteria, and methods. As a result of this realization there are or have been approximately eighteen initiatives within the ASME , Boiler and Pressure Vessel Code Section III, Division 1, in the form of proposed code cases and proposed code text changes designed to reduce these failure margins to more realistic values. For the most part these initiatives have concentrated on reclassifying seismic inertia stresses in the piping as secondary and increasing the allowable stress limits permitted by Section III of the ASME, Boiler Code. This paper focuses on the application of non-linear spectral analysis methods as a method to reduce the input seismic demand determination and thereby reduce the seismic failure margins. The approach is evaluated using the ASME Boiler Pressure Vessel Code Section III Subgroup on Design benchmark procedure as proposed by the Subgroup's Special Task Group on Integrated Piping Criteria. Using this procedure, criteria are compared to current code criterion and analysis methods, and several other of the currently proposed Boiler and Pressure Vessel, Section III, changes. Finally, the applicability of the non-linear spectral analysis to continued Safe Operation Evaluations is reviewed and discussed

  9. Application of the ASME-code-case N 47 to a typical thickwalled HTR-component made of Incoloy 800

    International Nuclear Information System (INIS)

    Kemter, F.; Schmidt, A.

    Several components of the HTR-plant are exposed to temperatures beyond 500 0 C, i.e. within the high-temperature range. The service life of those components is not only limited by fatigue damage but also mainly by creep damage and accumulated inelastic strain. These can be conservatively estimated according to the ASME-Code (high temperature part CC N47) by means of the results of elastic calculations, yet this simplified method to provide evidence often leads to calculated overloads such as the present case of the live steam collector of the steam generator of a HTR. For providing the evidence that the actual loads of the component are within permissible limits, comprehensive inelastic analyses have to be referred to in such a case. The two-dimensional inelastic analysis which is reported here in detail shows that the creep and fatigue failure as well as the inelastic extensions of the live steam collectors accumulated during the service time are below the permissible limit stated in the ASME-Code and failure of those components while used in the reactor can this be excluded. (orig.) [de

  10. IE Information Notice No. 85-33: Undersized nozzle-to-shell welded joints in tanks and heat exchangers constructed under the rules of the ASME boiler and vessel code

    International Nuclear Information System (INIS)

    Jordan, E.L.

    1993-01-01

    During the CAT (Construction Appraisal Team) inspections conducted at the River Bend, Shearon Harris, and Braidwood nuclear power projects, the NRC identified undersized nozzle-to-shell welded joints (ASME Category D joints) in tanks and heat exchangers manufactured by various vendors. Specifically, four main steam isolation valve air accumulator tanks were found to have undersized nozzle-to-shell joints at the River Bend plant; seven tanks were found to have undersized nozzle-to-shell weld reinforcements at the Shearon Harris Station; eight tanks and two heat exchangers were found to have undersized nozzle-to-shell weld reinforcements at Braidwood Station. These tanks and heat exchangers were Code stamped and certified as being constructed in accordance with the requirements of the ASME Code. The ASME Code, Section III (NX-3352.4) requires that nozzle-to-shell welded joints have reinforcement (t c ) of 0.7t p or 1/4 inch, whichever is less, where t p is the thickness of the penetrating part. Some of the inspected welded joints did not have the minimum weld reinforcement (t c ) required by the Code. Other joints had the minimum weld reinforcement (t c ) required by the Code, but were found to be undersized with respect to the sizes specified on the applicable construction drawings

  11. The 1997 NRC IST workshops and the status of questions and issues directed to the ASME O and M committee

    International Nuclear Information System (INIS)

    DiBiasio, A.M.

    1998-05-01

    This paper describes the results of the four NRC Inservice Testing (IST) Workshops which were held in early 1997 pertaining to NRC Inspection Procedure P 73756, Inservice Testing of Pumps and Valves. It also presents the status of the ASME code committees' resolution of certain questions forwarded to the ASME by the NRC. These questions relate to code interpretations, inconsistencies in the code, and industry concerns that are most appropriately resolved through the ASME consensus process. The ASME committees reviewed the questions at their December 1997 and March 1998 code meetings. Of particular interest are those questions for which the ASME code committees did not agree with the NRC response. These questions, as well as those which the committees provided some additional insight or input, are presented in this paper

  12. An example of a component replacement when applying ASME N509 and ASME N510 to older ventilation systems

    Energy Technology Data Exchange (ETDEWEB)

    Arndt, T.E. [Westinghouse Hanford Company, Richland, WA (United States)

    1995-02-01

    This paper presents an example of a component replacement (electric heater) when installed in an older ventilation system that was constructed before the issuance of ASME N509{sup 1} and N510{sup 2}. Many of the existing ventilation systems at the Hanford Site were designed, fabricated, and installed before the issuance of ASME N509{sup 1} and N510{sup 2}. Requiring the application of these codes to existing ventilation systems presents challenges to the engineer when design changes are needed. Although it may seem that the application of ASME N509{sup 1} or N510{sup 2} may be a hindrance at times, this does not need to occur. Proper preparation at the start of project or design modifications can minimize frustration to the engineer when it is judged that portions of ASME N509{sup 1} and N510{sup 2} do not apply in a particular application.

  13. The application of RCM to ASME code requirements for in-service testing

    International Nuclear Information System (INIS)

    Rowley, C.W.

    1990-01-01

    This paper reports that the high reliability of nuclear power plant systems and components is highly important for both nuclear safety and electrical power production economics. The optimum operating performance of these plant systems and components is heavily dependent on the original or modified design for its inherent reliability and the appropriate trade-off in preventive and corrective maintenance for its developed reliability. In developing this optimum operating performance goal, the plant staff could rely solely on the experience of its personnel. However using this internal subjective approach, the average nuclear power availability has been far less than 80%. Obviously the production economics of a nuclear power plant is the province of the owner-operator, but the safety system and component performance impacts the entire industry. Hence the nuclear industry needs to have in-service testing requirements that maintain the necessary safety standards. Historically the ASME Inservice Testing Code has been a vehicle for defining some of those necessary safety standards, such as inservice testing of pumps, valves, and snubbers. The nuclear industry needs to expand the code testing to include all the systems that affect these necessary safety standards

  14. Highlights of proposed changes to ANSI/ASME N509-80

    International Nuclear Information System (INIS)

    Ornberg, S.C.

    1987-01-01

    The ASME Committee on Nuclear Air and Gas Treatment (CONAGT) are at the time of this writing considering performing maintenance revisions of ANSI N509 and N510 based on the results of a required 5-year review and comments received from users of the standards at workshops and through inquiries. This paper discusses the highlights of the significant revisions to ANSI/ASME N509 and explains the reasons for the changes. It should be emphasized that these revisions are not yet approved by ASME CONAGT, the board of Nuclear Codes and Standards, or ANSI

  15. New methods of analysis of materials strength data for the ASME Boiler and Pressure Vessel Code

    International Nuclear Information System (INIS)

    Booker, M.K.; Booker, B.L.P.

    1980-01-01

    Tensile and creep data of the type used to establish allowable stress levels for the ASME Boiler and Pressure Vessel Code have been examined for type 321H stainless steel. Both inhomogeneous, unbalanced data sets and well-planned homogeneous data sets have been examined. Data have been analyzed by implementing standard manual techniques on a modern digital computer. In addition, more sophisticated techniques, practical only through the use of the computer, have been applied. The result clearly demonstrates the efficacy of computerized techniques for these types of analyses

  16. Application of the ASME code in designing containment vessels for packages used to transport radioactive materials

    International Nuclear Information System (INIS)

    Raske, D.T.; Wang, Z.

    1992-01-01

    The primary concern governing the design of shipping packages containing radioactive materials is public safety during transport. When these shipments are within the regulatory jurisdiction of the US Department of Energy, the recommended design criterion for the primary containment vessel is either Section III or Section VIII, Division 1, of the ASME Boiler and Pressure Vessel Code, depending on the activity of the contents. The objective of this paper is to discuss the design of a prototypic containment vessel representative of a packaging for the transport of high-level radioactive material

  17. Comparisons of ASME-code fatigue-evaluation methods for nuclear Class 1 piping with Class 2 or 3 piping

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.

    1983-06-01

    The fatigue evaluation procedure used in the ASME Boiler and Pressure Vessel Code, Sect. III, Nuclear Power Plant Components, for Class 1 piping is different from the procedure used for Class 2 or 3 piping. The basis for each procedure is described, and correlations between the two procedures are presented. Conditions under which either procedure or both may be unconservative are noted. Potential changes in the Class 2 or 3 piping procedure to explicitly cover all loadings are discussed. However, the report is intended to be informative, and while the contents of the report may guide future Code changes, specific recommendations are not given herein

  18. Dynamic fracture toughness of ASME SA508 Class 2a ASME SA533 grade A Class 2 base and heat affected zone material and applicable weld metals

    International Nuclear Information System (INIS)

    Logsdon, W.A.; Begley, J.A.; Gottshall, C.L.

    1978-03-01

    The ASME Boiler and Pressure Vessel Code, Section III, Article G-2000, requires that dynamic fracture toughness data be developed for materials with specified minimum yield strengths greater than 50 ksi to provide verification and utilization of the ASME specified minimum reference toughness K/sub IR/ curve. In order to qualify ASME SA508 Class 2a and ASME SA533 Grade A Class 2 pressure vessel steels (minimum yield strengths equal 65 kip/in. 2 and 70 kip/in. 2 , respectively) per this requirement, dynamic fracture toughness tests were performed on these materials. All dynamic fracture toughness values of SA508 Class 2a base and HAZ material, SA533 Grade A Class 2 base and HAZ material, and applicable weld metals exceeded the ASME specified minimum reference toughness K/sub IR/ curve

  19. ASME Section XI philosophy related to operating nuclear plant fatigue damage protection

    International Nuclear Information System (INIS)

    Gosselin, S.R.

    1995-01-01

    When faced with operating fatigue concerns, nuclear plants traditionally look to the requirements contained in the original construction design code, ASME Section 3, as a basis for component operability. These rules constitute the requirements for nuclear power plant vessel and component construction and, when combined with the Owner's Design Specification, provide reasonable assurance of reliable operation. However, once construction is complete and operation begins, the purpose of any subsequent evaluations shifts from component ''design qualification'' to component ''fitness for service.'' This is a role that has been assumed for ASME Section 11. This paper presents a philosophy, recently endorsed by the ASME Section 11 Executive Committee, intended to guide future Code activities regarding fatigue and its impact on component serviceability

  20. Evaluation of conservatisms and environmental effects in ASME Code, Section III, Class 1 fatigue analysis

    International Nuclear Information System (INIS)

    Deardorff, A.F.; Smith, J.K.

    1994-08-01

    This report documents the results of a study regarding the conservatisms in ASME Code Section 3, Class 1 component fatigue evaluations and the effects of Light Water Reactor (LWR) water environments on fatigue margins. After review of numerous Class 1 stress reports, it is apparent that there is a substantial amount of conservatism present in many existing component fatigue evaluations. With little effort, existing evaluations could be modified to reduce the overall predicted fatigue usage. Areas of conservatism include design transients considerably more severe than those experienced during service, conservative grouping of transients, conservatisms that have been removed in later editions of Section 3, bounding heat transfer and stress analysis, and use of the ''elastic-plastic penalty factor'' (K 3 ). Environmental effects were evaluated for two typical components that experience severe transient thermal cycling during service, based on both design transients and actual plant data. For all reasonable values of actual operating parameters, environmental effects reduced predicted margins, but fatigue usage was still bounded by the ASME Section 3 fatigue design curves. It was concluded that the potential increase in predicted fatigue usage due to environmental effects should be more than offset by decreases in predicted fatigue usage if re-analysis were conducted to reduce the conservatisms that are present in existing component fatigue evaluations

  1. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    International Nuclear Information System (INIS)

    1994-07-01

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately

  2. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.

  3. Utility experience in code updating of equipment built to 1974 code, Section 3, Subsection NF

    International Nuclear Information System (INIS)

    Rao, K.R.; Deshpande, N.

    1990-01-01

    This paper addresses changes to ASME Code Subsection NF and reconciles the differences between the updated codes and the as built construction code, of ASME Section III, 1974 to which several nuclear plants have been built. Since Section III is revised every three years and replacement parts complying with the construction code are invariably not available from the plant stock inventory, parts must be procured from vendors who comply with the requirements of the latest codes. Aspects of the ASME code which reflect Subsection NF are identified and compared with the later Code editions and addenda, especially up to and including the 1974 ASME code used as the basis for the plant qualification. The concern of the regulatory agencies is that if later code allowables and provisions are adopted it is possible to reduce the safety margins of the construction code. Areas of concern are highlighted and the specific changes of later codes are discerned; adoption of which, would not sacrifice the intended safety margins of the codes to which plants are licensed

  4. Probabilistic evaluation of design S-N curve and reliability assessment of ASME code-based evaluation

    International Nuclear Information System (INIS)

    Zhao Yongxiang

    1999-01-01

    A probabilistic evaluating approach of design S-N curve and a reliability assessment approach of the ASME code-based evaluation are presented on the basis of Langer S-N model-based P-S-N curves. The P-S-N curves are estimated by a so-called general maximum likelihood method. This method can be applied to deal with the virtual stress amplitude-crack initial life data which have a characteristics of double random variables. Investigation of a set of the virtual stress amplitude-crack initial life (S-N) data of 1Cr18Ni9Ti austenitic stainless steel-welded joint reveals that the P-S-N curves can give a good prediction of scatter regularity of the S-N data. Probabilistic evaluation of the design S-N curve with 0.9999 survival probability has considered various uncertainties, besides of the scatter of the S-N data, to an appropriate extent. The ASME code-based evaluation with 20 reduction factor on the mean life is much more conservative than that with 2 reduction factor on the stress amplitude. Evaluation of the latter in 666.61 MPa virtual stress amplitude is equivalent to 0.999522 survival probability and in 2092.18 MPa virtual stress amplitude equivalent to 0.9999999995 survival probability. This means that the evaluation in the low loading level may be non-conservative and in contrast, too conservative in the high loading level. Cause is that the reduction factors are constants and the factors can not take into account the general observation that scatter of the N data increases with the loading level decreasing. This has indicated that it is necessary to apply the probabilistic approach to the evaluation of design S-N curve

  5. ASME factory authorization system and the situation in Japan

    International Nuclear Information System (INIS)

    Futagawa, Kiyoshi

    1978-01-01

    Since about three or four years ago, the enterprises of machinery, iron and steel and welding materials in Japan are paying much attention to the acquisition of ASME (American Society of Mechanical Engineers) certificates or authorization to stamp the code symbols. That is, over 70 factories in Japan have undergone ASME examination, and consequently acquired the authorization or certificates. Such authorization is divided into over 20 kinds, of which about 7 are possessed by the companies in Japan. In nuclear field, the kinds of authorization are N (nuclear vessel), NPT (nuclear vessel parts), NV (nuclear vessel safety valve), and MM (material manufacturing). In non-nuclear fields, they are S (power boilers), U (pressure vessels, in Div. 1), and U2 (pressure vessels in Div. 2). The following matters are described: ASME setup, authorization procedures of ASME for factories, the kinds of authorization, factories in Japan holding the authorization or certificates, and renewal of the authorization. (Mori, K.)

  6. Rulemaking efforts on codes and standards

    International Nuclear Information System (INIS)

    Millman, G.C.

    1992-01-01

    Section 50.55a of the NRC regulations provides a mechanism for incorporating national codes and standards into the regulatory process. It incorporates by reference ASME Boiler and Pressure Vessel Code (ASME B and PV Code) Section 3 rules for construction and Section 11 rules for inservice inspection and inservice testing. The regulation is periodically amended to update these references. The rulemaking process, as applied to Section 50.55a amendments, is overviewed to familiarize users with associated internal activities of the NRC staff and the manner in which public comments are integrated into the process. The four ongoing rulemaking actions that would individually amend Section 50.55a are summarized. Two of the actions would directly impact requirements for inservice testing. Benefits accrued with NRC endorsement of the ASME B and PV Code, and possible future endorsement of the ASME Operations and Maintenance Code (ASME OM Code), are identified. Emphasis is placed on the need for code writing committees to be especially sensitive to user feedback on code rules incorporated into the regulatory process to ensure that the rules are complete, technically accurate, clear, practical, and enforceable

  7. Evaluation of the integrity of reactor vessels designed to ASME Code, Sections I and/or VIII

    International Nuclear Information System (INIS)

    Hoge, K.G.

    1976-01-01

    A documented review of nuclear reactor pressure vessels designed to ASME Code, Sections I and/or VIII is made. The review is primarily concerned with the design specifications and quality assurance programs utilized for the reactor vessel construction and the status of power plant material surveillance programs, pressure-temperature operating limits, and inservice inspection programs. The following ten reactor vessels for light-water power reactors are covered in the report: Indian Point Unit No. 1, Dresden Unit No. 1, Yankee Rowe, Humboldt Bay Unit No. 3, Big Rock Point, San Onofre Unit No. 1, Connecticut Yankee, Oyster Creek, Nine Mile Point Unit No. 1, and La Crosse

  8. Investigating ASME allowable loads with finite element analyses

    International Nuclear Information System (INIS)

    Mattar Neto, Miguel; Bezerra, Luciano M.; Miranda, Carlos A. de J.; Cruz, Julio R.B.

    1995-01-01

    The evaluation of nuclear components using finite element analysis (FEA) does not generally fall into the shell type verification adopted by the ASME Code. Consequently, the demonstration that the modes of failure are avoided sometimes is not straightforward. Allowable limits, developed by limit load theory, require the computation of shell membrane and bending stresses. How to calculate these stresses from FEA is not necessarily self-evident. One approach to be considered is to develop recommendations in a case-by-case basis for the most common pressure vessel geometries and loads based on comparison between the results of elastic and plastic FEA. In this paper, FE analyses of common 2D and complex 3D geometries are examined and discussed. It will be clear that in the cases studied, stress separation and categorization are not self-evident and simple tasks to undertake. Certain unclear recommendations of ASME Code can lead the stress analyst to non conservative designs as will be demonstrated in this paper. At the endo of this paper, taking into account comparison between elastic and elastic-plastic FE results from ANSYS some observations, suggestions and conclusions about the degree of conservatism of the ASME recommendations will be addressed. (author)

  9. NRC needs and their implementation-ASME Section IX code

    International Nuclear Information System (INIS)

    Liaw, B.D.

    1985-01-01

    The guiding principle from the onset of government regulation for the peaceful use of nuclear energy has been to prescribe only the minimum requirements that are needed for safety. In the pioneer regulators' collective mind, the technical details could be left to the regulated industry through its agents like NSSS vendors and A/E's and their surrogate organizations like ASME, ANS, AIF, etc. However, it has evolved through the years, due either to the bureaucratic momentum or the vacuum in industry leadership, into a situation where one sees an ever increasing number of detailed ''requirements'' prescribed by the regulators. Within the scope of activities covered by Section XI, there is no exception: e.g., NUREG-067, -0531 -1061; NUREG-0313 Rev. 0, Rev. 1, and now Rev. 2; IE Bulletins 82-03, 83-02; and Generic Letters 84-11, and 84-07, etc. for one issue of pipe crack alone; and there are more to come. There appears a consensus among all concerned parties including regulators that this is not a desirable situation and that something must be done to reverse this trend. The purpose of this discussion is, therefore, to explore the areas where the Section XI Code can be restructured to meet this need, and to seek ideas from the representatives of the regulated industry on the methods of implementation that are effective, efficient, and acceptable to all concerned parties

  10. Summary of design of nuclear vessels and piping to ASME III (NB, NC, ND) and vessels to BS 5500

    International Nuclear Information System (INIS)

    Harrop, L.P.

    1992-01-01

    There is a hierarchy of design code requirements for pressurised components, starting with non-nuclear codes as the minimum and progressing through the ASME III nuclear Classes 3, 2, 1. In establishing and assessing the safety justifications of nuclear plants it is important to have an appreciation of the gradation of requirements in the ASME III design rules and how these go beyond non-nuclear component design rules. There are two broad aspects to the structural integrity of pressurised components, namely the achievement of integrity and the demonstration of integrity. The technical requirements of design codes are associated with achieving integrity while the documentary aspects are usually associated with demonstrating integrity. In practice documents also have a part in achieving integrity in the communication of information between different organisations and personnel involved in the design process. It is not possible to assign simple numerical measures to the relative integrity afforded by non-nuclear codes and the three Classes of ASME III. Instead it is necessary to compare the different requirements of the rules for the various technical and documentary aspects. This paper summarises the most important technical and documentary aspects of the three Classes of the ASME III Code for vessels and the non-nuclear code BS 5500. A similar summary is also provided for the three Classes of ASME III rules for piping. The intention is that the paper provides a basis for appreciating the relative integrity afforded by these various rules. (author)

  11. The ASME Section 11 Special Working Group On Plant Life Extension

    International Nuclear Information System (INIS)

    Katz, L.R.

    1990-01-01

    The codes and standards applicable to plant life extension have not been identified in the U.S. at this time. However, several initiatives have been taken to establish specific codes and standards pertaining to nuclear plant life extension (PLEX). One of these initiatives, sponsored by ASME, is the Section XI Special Working Group on Plant Life Extension (SWG-PLEX). The SWG-PLEX reports to the ASME Section XI Subcommittee and is responsible for recommending or drafting rules and requirements for modifying Section XI to accommodate age-related degradation to support nuclear plant life extension. This paper summarizes the results and reports the activities of the SWG-PLEX during the 1989/1990 period

  12. Development of a software for the ASME code qualification of class-I nuclear piping systems

    International Nuclear Information System (INIS)

    Mishra, Rajesh; Umashankar, C.; Soni, R.S.; Kushwaha, H.S.; Venkat Raj, V.

    1999-11-01

    In nuclear industry, the designer often comes across the requirements of Class-1 piping systems which need to be qualified for various normal and abnormal loading conditions. In order to have quick design changes and the design reviews at various stages of design, it is quite helpful if a dedicated software is available for the qualification of Class-1 piping systems. BARC has already purchased a piping analysis software CAESAR-II and has used it for the life extension of heavy water plant, Kota. CAESAR-II facilitates the qualification of Class-2 and Class-3 piping systems among others. However, the present version of CAESAR-II does not have the capability to perform stress checks for the ASME Class-1 nuclear piping systems. With this requirement in mind and the prohibitive costs of commercially available software for the Class-1 piping analyses, it was decided to develop a separate software for this class of piping in such a way that the input and output details of the piping from the CAESAR-II software can be made use of. This report principally contains the details regarding development of a software for codal qualification of Class-1 nuclear piping as per ASME code section-III, NB-3600. The entire work was carried out in three phases. The first phase consisted of development of the routines for reading the output files obtained from the CAESAR-II software, and converting them into required format for further processing. In this phase, the nodewise informations available from the CAESAR-II output file were converted into element-wise informations. The second phase was to develop a general subroutine for reading the various input parameters such as diameter, wall thickness, corrosion allowance, bend radius and also to recognize the bend elements based on the bend radius, directly from the input file of CAESAR-II software. The third phase was regarding the incorporation of the required steps for performing the ASME codal checks as per NB-3600 for Class-1 piping

  13. Interpreting ASME limits and philosophy in FEA of pressure vessel parts

    International Nuclear Information System (INIS)

    Bezerra, L.M.; Cruz, J.R.B.; Miranda, C.A.J.; Neto, M.M.

    1995-01-01

    In recent years there has been an effort to interpret finite element (FE) stress results on the light of the ASME B and PV rules and philosophy. Many task groups have issued guidelines on stress linearization and classifications. All those attempts have come up trying to cope modern FE techniques with the rules imposed by the ASME Code. This paper is an independent contribution to the Pressure Vessel Research Council (PVRC) groups which are studying the stress classification and the failure mechanism in a FE framework. This work tries to complement the interesting work by Hollinger and Hechmer presented in the PVP-94 in Minneapolis. In that paper, the authors examined a typical support skirt and showed relations between the skirt collapse load obtained by finite element analysis and the loads allowed from the ASME stress limits. To complement such paper, in the present article, different skirt geometry configurations are analyzed. The configurations here investigated consist of similar support skirts but with different angles of attachments between cylinder and cone parts. It will be possible to observe the influence of the bending stress in the collapse load and its relation to the allowable loads inferred from the ASME limits. A pressure vessel with torispherical head under internal pressure is also examined. Using elastic and limit load FEA, the present paper determines the collapse loads of the configurations. It sets up the relations between these collapse loads, stress categories, and limits dictated by the ASME Code Subsection NB. On the light of NB rules and philosophy, this paper shows how different methods of stress assessment, classification, and limits may influence in the design of a pressure vessel

  14. ASME code considerations for the compact heat exchanger

    Energy Technology Data Exchange (ETDEWEB)

    Nestell, James [MPR Associates Inc., Alexandria, VA (United States); Sham, Sam [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-08-31

    robustness. Classic shell and tube designs will be large and costly, and may only be appropriate in steam generator service in the SHX where boiling inside the tubes occurs. For other energy conversion systems, all of these features can be met in a compact heat exchanger design. This report will examine some of the ASME Code issues that will need to be addressed to allow use of a Code-qualified compact heat exchanger in IHX or SHX nuclear service. Most effort will focus on the IHX, since the safety-related (Class A) design rules are more extensive than those for important-to-safety (Class B) or commercial rules that are relevant to the SHX.

  15. International pressure vessels and piping codes and standards. Volume 2: Current perspectives; PVP-Volume 313-2

    International Nuclear Information System (INIS)

    Rao, K.R.; Asada, Yasuhide; Adams, T.M.

    1995-01-01

    The topics in this volume include: (1) Recent or imminent changes to Section 3 design sections; (2) Select perspectives of ASME Codes -- Section 3; (3) Select perspectives of Boiler and Pressure Vessel Codes -- an international outlook; (4) Select perspectives of Boiler and Pressure Vessel Codes -- ASME Code Sections 3, 8 and 11; (5) Codes and Standards Perspectives for Analysis; (6) Selected design perspectives on flow-accelerated corrosion and pressure vessel design and qualification; (7) Select Codes and Standards perspectives for design and operability; (8) Codes and Standards perspectives for operability; (9) What's new in the ASME Boiler and Pressure Vessel Code?; (10) A look at ongoing activities of ASME Sections 2 and 3; (11) A look at current activities of ASME Section 11; (12) A look at current activities of ASME Codes and Standards; (13) Simplified design methodology and design allowable stresses -- 1 and 2; (14) Introduction to Power Boilers, Section 1 of the ASME Code -- Part 1 and 2. Separate abstracts were prepared for most of the individual papers

  16. ASME AG-1 Section FC Qualified HEPA Filters; a Particle Loading Comparison - 13435

    International Nuclear Information System (INIS)

    Stillo, Andrew; Ricketts, Craig I.

    2013-01-01

    High Efficiency Particulate Air (HEPA) Filters used to protect personnel, the public and the environment from airborne radioactive materials are designed, manufactured and qualified in accordance with ASME AG-1 Code section FC (HEPA Filters) [1]. The qualification process requires that filters manufactured in accordance with this ASME AG-1 code section must meet several performance requirements. These requirements include performance specifications for resistance to airflow, aerosol penetration, resistance to rough handling, resistance to pressure (includes high humidity and water droplet exposure), resistance to heated air, spot flame resistance and a visual/dimensional inspection. None of these requirements evaluate the particle loading capacity of a HEPA filter design. Concerns, over the particle loading capacity, of the different designs included within the ASME AG-1 section FC code[1], have been voiced in the recent past. Additionally, the ability of a filter to maintain its integrity, if subjected to severe operating conditions such as elevated relative humidity, fog conditions or elevated temperature, after loading in use over long service intervals is also a major concern. Although currently qualified HEPA filter media are likely to have similar loading characteristics when evaluated independently, filter pleat geometry can have a significant impact on the in-situ particle loading capacity of filter packs. Aerosol particle characteristics, such as size and composition, may also have a significant impact on filter loading capacity. Test results comparing filter loading capacities for three different aerosol particles and three different filter pack configurations are reviewed. The information presented represents an empirical performance comparison among the filter designs tested. The results may serve as a basis for further discussion toward the possible development of a particle loading test to be included in the qualification requirements of ASME AG-1

  17. ASME AG-1 Section FC Qualified HEPA Filters; a Particle Loading Comparison - 13435

    Energy Technology Data Exchange (ETDEWEB)

    Stillo, Andrew [Camfil Farr, 1 North Corporate Drive, Riverdale, NJ 07457 (United States); Ricketts, Craig I. [New Mexico State University, Department of Engineering Technology and Surveying Engineering, P.O. Box 30001 MSC 3566, Las Cruces, NM 88003-8001 (United States)

    2013-07-01

    High Efficiency Particulate Air (HEPA) Filters used to protect personnel, the public and the environment from airborne radioactive materials are designed, manufactured and qualified in accordance with ASME AG-1 Code section FC (HEPA Filters) [1]. The qualification process requires that filters manufactured in accordance with this ASME AG-1 code section must meet several performance requirements. These requirements include performance specifications for resistance to airflow, aerosol penetration, resistance to rough handling, resistance to pressure (includes high humidity and water droplet exposure), resistance to heated air, spot flame resistance and a visual/dimensional inspection. None of these requirements evaluate the particle loading capacity of a HEPA filter design. Concerns, over the particle loading capacity, of the different designs included within the ASME AG-1 section FC code[1], have been voiced in the recent past. Additionally, the ability of a filter to maintain its integrity, if subjected to severe operating conditions such as elevated relative humidity, fog conditions or elevated temperature, after loading in use over long service intervals is also a major concern. Although currently qualified HEPA filter media are likely to have similar loading characteristics when evaluated independently, filter pleat geometry can have a significant impact on the in-situ particle loading capacity of filter packs. Aerosol particle characteristics, such as size and composition, may also have a significant impact on filter loading capacity. Test results comparing filter loading capacities for three different aerosol particles and three different filter pack configurations are reviewed. The information presented represents an empirical performance comparison among the filter designs tested. The results may serve as a basis for further discussion toward the possible development of a particle loading test to be included in the qualification requirements of ASME AG-1

  18. ITER's Tokamak Cooling Water System and the the Use of ASME Codes to Comply with French Regulations of Nuclear Pressure Equipment

    International Nuclear Information System (INIS)

    Berry, Jan; Ferrada, Juan J.; Curd, Warren; Dell Orco, Giovanni; Barabash, Vladimir; Kim, Seokho H.

    2011-01-01

    During inductive plasma operation of ITER, fusion power will reach 500 MW with an energy multiplication factor of 10. The heat will be transferred by the Tokamak Cooling Water System (TCWS) to the environment using the secondary cooling system. Plasma operations are inherently safe even under the most severe postulated accident condition a large, in-vessel break that results in a loss-of-coolant accident. A functioning cooling water system is not required to ensure safe shutdown. Even though ITER is inherently safe, TCWS equipment (e.g., heat exchangers, piping, pressurizers) are classified as safety important components. This is because the water is predicted to contain low-levels of radionuclides (e.g., activated corrosion products, tritium) with activity levels high enough to require the design of components to be in accordance with French regulations for nuclear pressure equipment, i.e., the French Order dated 12 December 2005 (ESPN). ESPN has extended the practical application of the methodology established by the Pressure Equipment Directive (97/23/EC) to nuclear pressure equipment, under French Decree 99-1046 dated 13 December 1999, and Order dated 21 December 1999 (ESP). ASME codes and supplementary analyses (e.g., Failure Modes and Effects Analysis) will be used to demonstrate that the TCWS equipment meets these essential safety requirements. TCWS is being designed to provide not only cooling, with a capacity of approximately 1 GW energy removal, but also elevated temperature baking of first-wall/blanket, vacuum vessel, and divertor. Additional TCWS functions include chemical control of water, draining and drying for maintenance, and facilitation of leak detection/localization. The TCWS interfaces with the majority of ITER systems, including the secondary cooling system. U.S. ITER is responsible for design, engineering, and procurement of the TCWS with industry support from an Engineering Services Organization (ESO) (AREVA Federal Services, with support

  19. Case study of the propagation of a small flaw under PWR loading conditions and comparison with the ASME code design life. Comparison of ASME Code Sections III and XI

    International Nuclear Information System (INIS)

    Yahr, G.T.; Gwaltney, R.C.; Richardson, A.K.; Server, W.L.

    1986-01-01

    A cooperative study was performed by EG and G Idaho, Inc., and Oak Ridge National Laboratory to investigate the degree of conservatism and consistency in the ASME Boiler and Pressure Vessel Code Section III fatigue evaluation procedure and Section XI flaw acceptance standards. A single, realistic, sample problem was analyzed to determine the significance of certain points of criticism made of an earlier parametric study by staff members of the Division of Engineering Standards of the Nuclear Regulatory Commission. The problem was based on a semielliptical flaw located on the inside surface of the hot-leg piping at the reactor vessel safe-end weld for the Zion 1 pressurized-water reactor (PWR). Two main criteria were used in selecting the problem; first, it should be a straight pipe to minimize the computational expense; second, it should exhibit as high a cumulative usage factor as possible. Although the problem selected has one of the highest cumulative usage factors of any straight pipe in the primary system of PWRs, it is still very low. The Code Section III fatigue usage factor was only 0.00046, assuming it was in the as-welded condition, and fatigue crack-growth analyses predicted negligible crack growth during the 40-year design life. When the analyses were extended past the design life, the usage factor was less than 1.0 when the flaw had propagated to failure. The current study shows that the criticism of the earlier report should not detract from the conclusion that if a component experiences a high level of cyclic stress corresponding to a fatigue usage factor near 1.0, very small cracks can propagate to unacceptable sizes

  20. U.F.F.A.: A numerical procedure for fatigue analysis according to ASME code

    International Nuclear Information System (INIS)

    Bellettato, W.; Ticozzi, C.; Zucchini, C.

    1981-01-01

    A new procedure is developed, which employs some already used methodologies and brings some new concepts. The computer code UFFA employs the so obtained procedure. This paper in the first part describes the methodology used for the usage factor calculation, in the second part carries a general description of the code and in the third part shows some example and their respective results. We suppose an elastic behaviour of the materials and we do not consider the effect of the application order of the loads. Moreover, we suppose valid the hypothesis of cumulative damage, that is we apply the Miner's rule. One of the problems in the nuclear components fatigue analysis is that in the load histories there is a high number of operational cycles for which we cannot specify a succession in the time. Therefore, it was introduced the concept of 'level' (or steady working status) by which we can approximate the load conditions in realistic way. As regard the problem of multiaxial cases, it is possible to show that it is not right, an neither conservative, to make a distinguished analysis of the 3 stress differences and then take the maximum of the 3 compuoted usage factors as component usage factor. Indeed, as the stresses act on the structure at the same time, it is necessary a contemporary analysis of the 3 stress difference curves. The computer code can deal as well with the case of sher stresses (varying principal stress directions) through the ASME 'normalization' procedure. The results of the UFFA program, compared with the results of other programs used at present, come up to the expectations. (orig./HP)

  1. 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.

  2. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    Energy Technology Data Exchange (ETDEWEB)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P. [and others

    1996-12-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising.

  3. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    International Nuclear Information System (INIS)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P.

    1996-01-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising

  4. A Life-Cycle Risk-Informed Systems Structured Nuclear Code

    International Nuclear Information System (INIS)

    Hill, Ralph S. III

    2002-01-01

    Current American Society of Mechanical Engineers (ASME) nuclear codes and standards rely primarily on deterministic and mechanistic approaches to design. The design code is a separate volume from the code for inservice inspections and both are separate from the standards for operations and maintenance. The ASME code for inservice inspections and code for nuclear plant operations and maintenance have adopted risk-informed methodologies for inservice inspection, preventive maintenance, and repair and replacement decisions. The American Institute of Steel Construction and the American Concrete Institute have incorporated risk-informed probabilistic methodologies into their design codes. It is proposed that the ASME nuclear code should undergo a planned evolution that integrates the various nuclear codes and standards and adopts a risk-informed approach across a facility life-cycle - encompassing design, construction, operation, maintenance and closure. (author)

  5. Comparison of the ASME Environmental Fatigue Design Curve with the Leax' Low Bound Model

    International Nuclear Information System (INIS)

    Jeong, Ill Seok; Kim, Wan Jae; Jun, Hyun Ik

    2010-01-01

    Environmental fatigue issue long time argued between industry and regulator. The issues of the debates are about environmental fatigue data only from experiment laboratories, no evidences in fields, and over conservatism. However, NRC issued the requirement to implement it to the construction design prior to industry practical design code. American Society of Mechanical Engineers (ASME) determined to issue non-mandatory code cases of environmental fatigue design. This paper evaluated the conservatism of the ASME proposed environmental fatigue design curve in comparison with the Leax' low bound approach model of environmental fatigue curve. A group of CF8M cast austenitic stainless steel (CASS) produced in KEPCO Research Center was introduced in the evaluation

  6. Methodology and guidelines for evaluation of welded attachments on ASME Class 1,2, or 3 piping

    International Nuclear Information System (INIS)

    Chang, K.C.; Adams, T.M.; Rodabaugh, E.C.

    1985-01-01

    The ASME Boiler and Pressure Vessel Code, Section III Subsection NB/NC/ND-3600 provides simplified rules for the evaluation and qualification of piping components. The use of rectangular and hollow, circular welded attachments (hereafter called lugs and trunions) is sometimes necessary in order to provide support for piping systems. The Code provides a set of simple and conservative equations, the associated stress indicies, and specified limitations on their applicability for lugs on Class 1 and Class 2/3 piping in Code Cases N-122 and N-318 respectively. Two new ASME Section III Code Cases, N-391 and N-392, have been prepared to provide the corresponding design guidelines for specific trunion configurations. This paper presents the background on the major concepts involved in the development of these Code Cases and provides some general guidelines to the analysts and designers for the qualification of the attachments not covered by the Code Cases

  7. The adjoint sensitivity method, a contribution to the code uncertainty evaluation

    International Nuclear Information System (INIS)

    Ounsy, A.; Brun, B.; De Crecy, F.

    1994-01-01

    This paper deals with the application of the adjoint sensitivity method (ASM) to thermal hydraulic codes. The advantage of the method is to use small central processing unit time in comparison with the usual approach requiring one complete code run per sensitivity determination. In the first part the mathematical aspects of the problem are treated, and the applicability of the method of the functional-type response of a thermal hydraulic model is demonstrated. On a simple example of non-linear hyperbolic equation (Burgers equation) the problem has been analysed. It is shown that the formalism used in the literature treating this subject is not appropriate. A new mathematical formalism circumventing the problem is proposed. For the discretized form of the problem, two methods are possible: the continuous ASM and the discrete ASM. The equivalence of both methods is demonstrated; nevertheless only the discrete ASM constitutes a practical solution for thermal hydraulic codes. The application of the discrete ASM to the thermal hydraulic safety code CATHARE is then presented for two examples. They demonstrate that the discrete ASM constitutes an efficient tool for the analysis of code sensitivity. ((orig.))

  8. Comparisons of ratchetting analysis methods using RCC-M, RCC-MR and ASME codes

    International Nuclear Information System (INIS)

    Yang Yu; Cabrillat, M.T.

    2005-01-01

    The present paper compares the simplified ratcheting analysis methods used in RCC-M, RCC-MR and ASME with some examples. Firstly, comparisons of the methods in RCC-M and efficiency diagram in RCC-MR are investigated. A special method is used to describe these two methods with curves in one coordinate, and the different conservation is demonstrated. RCC-M method is also be interpreted by SR (second ratio) and v (efficiency index) which is used in RCC-MR. Hence, we can easily compare the previous two methods by defining SR as abscissa and v as ordinate and plotting two curves of them. Secondly, comparisons of the efficiency curve in RCC-MR and methods in ASME-NH APPENDIX T are investigated, with significant creep. At last, two practical evaluations are performed to show the comparisons of aforementioned methods. (authors)

  9. 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.

  10. ASME and RCC-MR comparison for the prevention of fatigue analysis

    International Nuclear Information System (INIS)

    Autrusson, B.; Acker, D.

    1989-01-01

    The purpose of this survey is to compare the simplified methods, without reference to the safety factor allowed for the mechanical properties. An application of both codes, RCC-MR and ASME, on the design of the wall mock-up of the NET project is made and also an estimation with an elastoplastic analysis. In the case of fatigue analysis according to ASME in the plastic field, the elastic stress is magnified by a K e factor derived from stress variation, S n , disregarding geometrical discontinuities. According to RCC-MR, the elastic maximum strain will magnified by two coefficients accounting for plasticity and variation of Poisson ratio

  11. ASME power test code ptc 4.1 for steam generators; Codigo de pruebas de potencia ASME ptc 4.1 para generadores de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Plauchu Alcantara, Jorge Alberto [Plauchu Consultores, Morelia, Michoacan (Mexico)

    2001-07-01

    This presentation is oriented towards those who in this subject have experience in the design and equipment specification, plant projects, factory and field testing, operation or result analyses. An important fraction of the national energy supply, approximately 13%, is applied to the steam generation in the different aspects of the industrial activity, in the electrical industry of public service and in the commercial and services sector. The development of the national programs of energy efficiency verifies this when dedicating to this use of the energy important projects, some of them with support of the USAID. The measurement of the energy utilization or the efficiency of steam generators (or boilers) is made applying some procedure agreed by the parts and the one of greater acceptance and best known in Mexico and internationally is the ASME Power Test Code PTC 4.1 for Steam Generators. The purpose and formality in the determination of efficiency and of steam generation capacity behavior, thermal basic regime or fulfillment of guarantees, radically changes the exigencies of strict attachment to the PTC 4.1 This definition will determine the importance of the test method selected, the deviations and convened exceptions, the influence of the precision and the measurement errors, the consideration of auxiliary equipment, etc. An interpretation or incorrect application of the Test Code has lead and will lead to results and nonreliable decisions. [Spanish] Esta exposicion se orienta a quienes en este tema cuenta con experiencia en diseno y especificacion de equipo, proyecto de planta, pruebas en fabrica y campo, operacion o analisis de resultados. Una fraccion importante de la oferta nacional de energia, 13% aproximadamente, se aplica a la generacion de vapor en diferentes giros de actividad industrial, en la industria electrica, de servicio publico y en el sector de servicios y comercial. El desarrollo de los programas nacionales de eficiencia energetica comprueba

  12. Applications of American design codes for elevated temperature environment

    International Nuclear Information System (INIS)

    Severud, L.K.

    1980-03-01

    A brief summary of the ASME Code rules of Case N-47 is presented. An overview of the typical procedure used to demonstrate Code compliance is provided. Application experience and some examples of detailed inelastic analysis and simplified-approximate methods are given. Recent developments and future trends in design criteria and ASME Code rules are also presented

  13. The ASME research task force on risk-based in-service inspection

    International Nuclear Information System (INIS)

    Balkey, K.R.; Chapman, O.J.V.

    1997-01-01

    The use of risk-based methods in the development of in-service inspection (ISI) and in-service testing (IST) programs for nuclear power plant and other industrial applications has been studied for the last several years through the American Society of Mechanical Engineers Centre for Research and Technology Development (ASME 1991, 1992, 1994, 1996). The results of this work are being used as a foundation to develop specific requirements for implementation of risk-based technology in ASME Codes and Standards, regulatory requirements and industry programs both in the U.S. and other countries. This paper provides a brief overview of the ASME Research Methodology and how it has been adapted for application to the inspection of piping within the USA. It also relates how the reliability of nondestructive examination (NDE) methods for pressure boundary components can impact the risk and discusses the relationship between this and NDE qualification/demonstration now being implemented in Europe and the USA. (orig.)

  14. Creep-fatigue damage evaluation for SS-316LN (ORNL PLATES): - RCC-MR vs. ASME SEC III - NH

    International Nuclear Information System (INIS)

    Sati, Bhuwan Chandra; Jalaldeen, S.; Velusamy, K.; Selvaraj, P.

    2016-01-01

    Investigations of high temperature tests done on ORNL plate with deformation control loading, under creep-fatigue damage have been presented. The test results with methodology of RCC-MR and ASME-NH life prediction under creep-fatigue loading have been assessed. The stress relaxation effect in calculating the life using RCC-MR under creep-fatigue damage is found to be significant in presence of secondary stress. RCC-MR: 2007 is more realistic number of cycles (predicts 51 number of cycles) as compared to ASME-NH (predicts 312 number of cycles) which is demonstrated by the experimental work (observed 86 numbers of cycles). Between RCC-MR and experimental work, design code seems to be more conservative for life prediction due to creep-fatigue damage. For fatigue damage, the approaches are same and the difference comes from material properties and the starting stress for applying Neuber's rule. ASME approach has the limitation of stress range magnitude. ASME approach predicts lower elastic plus plastic strain for the cases having S* above the linear stress limit. For creep strain and creep damage evaluation, ASME and RCC-MR have different approaches for calculating the stress at the beginning and during the hold period. The RCC-MR takes account of cyclic hardening or softening effects (hardening in the present case of 316 LN) by means of the cyclic stress-strain curve and the benefit of symmetrization effects which are significant for this material. The ASME code neglects these effects and instead relies on an approach based on the isochronous stress-strain curves. (author)

  15. Design evaluation on sodium piping system and comparison of the design codes

    International Nuclear Information System (INIS)

    Lee, Dong Won; Jeong, Ji Young; Lee, Yong Bum; Lee, Hyeong Yeon

    2015-01-01

    A large-scale sodium test loop of STELLA-1 (Sodium integral effect test loop for safety simulation and assessment) with two main piping systems has been installed at KAERI. In this study, design evaluations on the main sodium piping systems in STELLA-1 have been conducted according to the DBR (design by rule) codes of the ASME B31.1 and RCC-MRx RB-3600. In addition, design evaluations according to the DBA (design by analysis) code of the ASME Section III Subsection NB-3200 have been conducted. The evaluation results for the present piping systems showed that results from the DBR codes were more conservative than those from the DBA code, and among the DBR codes, the non-nuclear code of the ASME B31.1 was more conservative than the French nuclear DBR code of the RCC-MRx RB-3600. The conservatism on the DBR codes of the ASME B31.1 and RCC-MRx RB-3600 was quantified based on the present sodium piping analyses.

  16. Design evaluation on sodium piping system and comparison of the design codes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Won; Jeong, Ji Young; Lee, Yong Bum; Lee, Hyeong Yeon [KAERI, Daejeon (Korea, Republic of)

    2015-03-15

    A large-scale sodium test loop of STELLA-1 (Sodium integral effect test loop for safety simulation and assessment) with two main piping systems has been installed at KAERI. In this study, design evaluations on the main sodium piping systems in STELLA-1 have been conducted according to the DBR (design by rule) codes of the ASME B31.1 and RCC-MRx RB-3600. In addition, design evaluations according to the DBA (design by analysis) code of the ASME Section III Subsection NB-3200 have been conducted. The evaluation results for the present piping systems showed that results from the DBR codes were more conservative than those from the DBA code, and among the DBR codes, the non-nuclear code of the ASME B31.1 was more conservative than the French nuclear DBR code of the RCC-MRx RB-3600. The conservatism on the DBR codes of the ASME B31.1 and RCC-MRx RB-3600 was quantified based on the present sodium piping analyses.

  17. AIS ASM Operational Integration Plan

    Science.gov (United States)

    2013-08-01

    Rack mount computer AIS Radio Interface Ethernet Switch 192.168.0.x Firewall Cable Modem 192.168.0.1 VTS Accred. Boundary AIS ASM Operational... AIS ASM Operational Integration Plan Distribution Statement A: Approved for public release; distribution is unlimited. August 2013 Report No...CD-D-07-15 AIS ASM Operational Integration Plan ii UNCLAS//Public | CG-926 R&DC | I. Gonin, et al. | Public August 2013 N O T I C

  18. Replacement of radiography with ultrasonic phased array for feeder tubes in CANDU reactors using ASME code case N-659-2

    International Nuclear Information System (INIS)

    Simmons, R.; Bower, Q.; Arseneau, S.

    2013-01-01

    In this paper we will discuss phased array technology for the replacement of radiography on new construction projects in the nuclear industry. Specifically, through the implementation of A.S.M.E. code N-659-2 and MetaPhase phased array services. Phased Array is not considered a new technique on in service welds in the nuclear industry; however it was unprecedented on new construction welds and required significant investment in regulatory approval (C.N.S.C.), technology research and development, regulatory, client and technician training for successful service implementation. This paper will illustrate the abilities and limitations associated in replacing radiography with MetaPhase, as well as the substantial benefits relative to increased production, improved weld quality, enhanced safety and overall project cost savings. (author)

  19. A Survey of Variable Extragalactic Sources with XTE's All Sky Monitor (ASM)

    Science.gov (United States)

    Jernigan, Garrett

    1998-01-01

    The original goal of the project was the near real-time detection of AGN utilizing the SSC 3 of the ASM on XTE which does a deep integration on one 100 square degree region of the sky. While the SSC never performed sufficiently well to allow the success of this goal, the work on the project has led to the development of a new analysis method for coded aperture systems which has now been applied to ASM data for mapping regions near clusters of galaxies such as the Perseus Cluster and the Coma Cluster. Publications are in preparation that describe both the new method and the results from mapping clusters of galaxies.

  20. Risk-informed appendices G and E for section XI of the ASME Boiler and Pressure Vessel Code

    International Nuclear Information System (INIS)

    Carter, B; Spanner, J.; Server, W.; Gamble, R.; Bishop, B.; Palm, N.; Heinecke, C.

    2011-01-01

    Full text of publication follows: The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, contains two appendices (G and E) related to reactor pressure boundary integrity. Appendix G provides procedures for defining Service Level A and B pressure temperature limits for ferritic components in the reactor coolant pressure boundary. Recently, an alternative risk informed methodology has been developed for ASME Section XI, Appendix G. The alternative methodology provides simple procedures to define risk informed pressure temperature limits for Service Level A and B events, including leak testing and reactor start up and shut down for both pressurized water reactors (PWRs) and boiling water reactors (BWRs). Risk informed pressure temperature limits provide more operational flexibility, particularly for reactor pressure vessels (RPV) with relatively high irradiation levels and radiation sensitive materials. Appendix E of Section XI provides a methodology for assessing conditions when the Appendix G limits are exceeded. A similar risk informed methodology is being considered for Appendix E. The probabilistic fracture mechanics evaluations used to develop the risk informed relationships included appropriate material properties for the range of RPV materials in operating plants in the United States and operating history and system operational constraints in both BWRs and PWRs. The analysis results were used to define pressure temperature relationships that provide an acceptable level of risk, consistent with safety goals defined by the U.S. Nuclear Regulatory Commission. The alternative methodologies for Appendices G and E will provide greater operational flexibility, especially for Service Level A and B events that may adversely affect efficient and safe plant operation, such as low temperature over pressurization for PWRs and BWR leak testing. Overall, application of the risk informed appendices can result in increased plant

  1. The adjoint sensitivity method, a contribution to the code uncertainty evaluation

    International Nuclear Information System (INIS)

    Ounsy, A.; Crecy, F. de; Brun, B.

    1993-01-01

    The application of the ASM (Adjoint Sensitivity Method) to thermohydraulic codes, is examined. The advantage of the method is to be very few CPU time consuming in comparison with usual approach requiring one complete code run per sensitivity determination. The mathematical aspects of the problem are first described, and the applicability of the method of the functional-type response of a thermalhydraulic model is demonstrated. On a simple example of non linear hyperbolic equation (Burgers equation) the problem has been analyzed. It is shown that the formalism used in the literature treating this subject is not appropriate. A new mathematical formalism circumventing the problem is proposed. For the discretized form of the problem, two methods are possible: the Continuous ASM and the Discrete ASM. The equivalence of both methods is demonstrated; nevertheless only the DASM constitutes a practical solution for thermalhydraulic codes. The application of the DASM to the thermalhydraulic safety code CATHARE is then presented for two examples. They demonstrate that ASM constitutes an efficient tool for the analysis of code sensitivity. (authors) 7 figs., 5 tabs., 8 refs

  2. The adjoint sensitivity method. A contribution to the code uncertainty evaluation

    International Nuclear Information System (INIS)

    Ounsy, A.; Brun, B.

    1993-01-01

    The application of the ASM (Adjoint Sensitivity Method) to thermohydraulic codes, is examined. The advantage of the method is to be very few CPU time consuming in comparison with usual approach requiring one complete code run per sensitivity determination. The mathematical aspects of the problem are first described, and the applicability of the method of the functional-type response of a thermalhydraulic model is demonstrated. On a simple example of non linear hyperbolic equation (Burgers equation) the problem has been analyzed. It is shown that the formalism used in the literature treating this subject is not appropriate. A new mathematical formalism circumventing the problem is proposed. For the discretized form of the problem, two methods are possible: the Continuous ASM and the Discrete ASM. The equivalence of both methods is demonstrated; nevertheless only the DASM constitutes a practical solution for thermalhydraulic codes. The application of the DASM to the thermalhydraulic safety code CATHARE is then presented for two examples. They demonstrate that ASM constitutes an efficient tool for the analysis of code sensitivity. (authors) 7 figs., 5 tabs., 8 refs

  3. The adjoint sensitivity method. A contribution to the code uncertainty evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Ounsy, A; Brun, B

    1994-12-31

    The application of the ASM (Adjoint Sensitivity Method) to thermohydraulic codes, is examined. The advantage of the method is to be very few CPU time consuming in comparison with usual approach requiring one complete code run per sensitivity determination. The mathematical aspects of the problem are first described, and the applicability of the method of the functional-type response of a thermalhydraulic model is demonstrated. On a simple example of non linear hyperbolic equation (Burgers equation) the problem has been analyzed. It is shown that the formalism used in the literature treating this subject is not appropriate. A new mathematical formalism circumventing the problem is proposed. For the discretized form of the problem, two methods are possible: the Continuous ASM and the Discrete ASM. The equivalence of both methods is demonstrated; nevertheless only the DASM constitutes a practical solution for thermalhydraulic codes. The application of the DASM to the thermalhydraulic safety code CATHARE is then presented for two examples. They demonstrate that ASM constitutes an efficient tool for the analysis of code sensitivity. (authors) 7 figs., 5 tabs., 8 refs.

  4. The adjoint sensitivity method, a contribution to the code uncertainty evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Ounsy, A; Crecy, F de; Brun, B

    1994-12-31

    The application of the ASM (Adjoint Sensitivity Method) to thermohydraulic codes, is examined. The advantage of the method is to be very few CPU time consuming in comparison with usual approach requiring one complete code run per sensitivity determination. The mathematical aspects of the problem are first described, and the applicability of the method of the functional-type response of a thermalhydraulic model is demonstrated. On a simple example of non linear hyperbolic equation (Burgers equation) the problem has been analyzed. It is shown that the formalism used in the literature treating this subject is not appropriate. A new mathematical formalism circumventing the problem is proposed. For the discretized form of the problem, two methods are possible: the Continuous ASM and the Discrete ASM. The equivalence of both methods is demonstrated; nevertheless only the DASM constitutes a practical solution for thermalhydraulic codes. The application of the DASM to the thermalhydraulic safety code CATHARE is then presented for two examples. They demonstrate that ASM constitutes an efficient tool for the analysis of code sensitivity. (authors) 7 figs., 5 tabs., 8 refs.

  5. Relationship between various pressure vessel and piping codes

    International Nuclear Information System (INIS)

    Canonico, D.A.

    1976-01-01

    Section VIII of the ASME Code provides stress allowable values for material specifications that are provided in Section II Parts A and B. Since the adoption of the ASME Code over 60 years ago the incidence of failure has been greatly reduced. The Codes are currently based on strength criteria and advancements in the technology of fracture toughness and fracture mechanics should permit an even greater degree of reliability and safety. This lecture discusses the various Sections of the Code. It describes the basis for the establishment of design stress allowables and promotes the idea of the use of fracture mechanics

  6. Enactment of KEPIC MNH Based on 2007 ASME BPVC Section III Division 1, Subsection NH: Class 1 Components in Elevated Temperature Service

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Kim, J. B.; Lee, H. Y.; Park, C. G.

    2008-11-01

    This report is a draft of an enactment of KEPIC MNH based on 2007 ASME Boiler and Pressure Vessel Code, Section III, Division 1 Subsection NH for Class 1 Components in Elevated Temperature Service and contains of ASME Article NH-3000 design, the mandatory appendix I-14, and non-mandatory appendices T and X

  7. Enactment of KEPIC MNH Based on 2007 ASME BPVC Section III Division 1, Subsection NH: Class 1 Components in Elevated Temperature Service

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Kim, J. B.; Lee, H. Y.; Park, C. G

    2008-11-15

    This report is a draft of an enactment of KEPIC MNH based on 2007 ASME Boiler and Pressure Vessel Code, Section III, Division 1 Subsection NH for Class 1 Components in Elevated Temperature Service and contains of ASME Article NH-3000 design, the mandatory appendix I-14, and non-mandatory appendices T and X.

  8. Preliminary application of the draft code case for alloy 617 for a high temperature component

    International Nuclear Information System (INIS)

    Lee, Hyeong Yeon; Kim, Yong Wan; Song, Kee Nam

    2008-01-01

    The ASME draft Code Case for Alloy 617 was developed in the late 1980s for the design of very-high-temperature gas cooled reactors. The draft Code Case was patterned after the ASME Code Section III Subsection NH and was intended to cover Ni-Cr-Co-Mo Alloy 617 to 982 .deg. C (1800 .deg. F). But the draft Code Case is still in an incomplete status, lacking necessary material properties and design data. In this study, a preliminary evaluation on the creep-fatigue damage for a high temperature hot duct pipe structure has been carried out according to the draft Code Case. The evaluation procedures and results according to the draft Code Case for Alloy 617 material were compared with those of the ASME Subsection NH and RCC-MR for Alloy 800H material. It was shown that many data including material properties, fatigue and creep data should be supplemented for the draft Code Case. However, when the evaluation results on the creep-fatigue damage according to the draft Code Case, ASME-NH and RCC-MR were compared based on the preliminary evaluation, it was shown that the Alloy 617 results from the draft Code Case tended to be more resistant to the creep damage while less resistant to the fatigue damage than those from the ASME-NH and RCC-MR

  9. ASTM and ASME-BPE Standards--Complying with the Needs of the Pharmaceutical Industry.

    Science.gov (United States)

    Huitt, William M

    2011-01-01

    Designing and building a pharmaceutical facility requires the owner, engineer of record, and constructor to be knowledgeable with regard to the industry codes and standards that apply to this effort. Up until 1997 there were no industry standards directed at the needs and requirements of the pharmaceutical industry. Prior to that time it was a patchwork effort at resourcing and adopting nonpharmaceutical-related codes and standards and then modifying them in order to meet the more stringent requirements of the Food and Drug Administration (FDA). In 1997 the American Society of Mechanical Engineers (ASME) published the first Bioprocessing Equipment (BPE) Standard. Through harmonization efforts this relatively new standard has brought together, scrutinized, and refined industry accepted methodologies together with FDA compliance requirements, and has established an American National Standard that provides a comprehensive set of standards that are integral to the pharmaceutical industry. This article describes various American National Standards, including those developed and published by the American Society for Testing and Materials (ASTM), and how they apply to the pharmaceutical industry. It goes on to discuss the harmonization effort that takes place between the various standards developers in an attempt to prevent conflicts and omissions between the many standards. Also included are examples of tables and figures taken from the ASME-BPE Standard. These examples provide the reader with insight to the relevant content of the ASME-BPE Standard. Designing and building a pharmaceutical facility requires the owner, engineer of record, and constructor to be knowledgeable with regard to the industry codes and standards that apply to this effort. Up until 1997 there were no industry standards directed at the needs and requirements of the pharmaceutical industry. Prior to that time it was a patchwork effort at resourcing and adopting nonpharmaceutical-related codes and

  10. Comparison of ASME pressure–temperature limits on the fracture probability for a pressurized water reactor pressure vessel

    International Nuclear Information System (INIS)

    Chou, Hsoung-Wei; Huang, Chin-Cheng

    2017-01-01

    Highlights: • P-T limits based on ASME K_I_a curve, K_I_C curve and RI method are presented. • Probabilistic and deterministic methods are used to evaluate P-T limits on RPV. • The feasibility of substituting P-T curves with more operational is demonstrated. • Warm-prestressing effect is critical in determining the fracture probability. - Abstract: The ASME Code Section XI-Appendix G defines the normal reactor startup (heat-up) and shut-down (cool-down) operation limits according to the fracture toughness requirement of reactor pressure vessel (RPV) materials. This paper investigates the effects of different pressure-temperature limit operations on structural integrity of a Taiwan domestic pressurized water reactor (PWR) pressure vessel. Three kinds of pressure-temperature limits based on different fracture toughness requirements – the K_I_a fracture toughness curve of ASME Section XI-Appendix G before 1998 editions, the K_I_C fracture toughness curve of ASME Section XI-Appendix G after 2001 editions, and the risk-informed revision method supplemented in ASME Section XI-Appendix G after 2013 editions, respectively, are established as the loading conditions. A series of probabilistic fracture mechanics analyses for the RPV are conducted employing ORNL’s FAVOR code considering various radiation embrittlement levels under these pressure-temperature limit conditions. It is found that the pressure-temperature operation limits which provide more operational flexibility may lead to higher fracture risks to the RPV. The cladding-induced shallow surface breaking flaws are the most critical and dominate the fracture probability of the RPV under pressure-temperature limit transients. Present study provides a risk-informed reference for the operation safety and regulation viewpoint of PWRs in Taiwan.

  11. The ASME Boiler and Pressure Vessel Code: overview

    International Nuclear Information System (INIS)

    Farr, J.R.

    1987-01-01

    To become familiar with the Boiler and Pressure Vessel Code of the American Society of Mechanical Engineers, it is necessary to understand the history, organization, and operation of the Boiler Code Committee as well as to become familiar with the important aspects of each Section of the Code. This chapter will review the background and contents of the Code as well as give a review of the salient contents of most sections. (author)

  12. Topical Session on Funding Issues in Connection with Decommissioning of Nuclear Power Plants - 9 November 2004

    International Nuclear Information System (INIS)

    2006-01-01

    Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Co-operative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the other NEA Committees. The EC is a member of the WPDD and the IAEA is participating as an observer. This broad participation provides good possibilities for the co-ordination efforts amongst activities in the international programmes. At its fifth meeting, in Paris, 8-10 November 2004, the WPDD held a topical session on the 'Funding Issues in Connection with Decommissioning of Nuclear Power Plants'. This report documents the topical session on Funding. An agenda of the Topical session can be found in Appendix 1. The topical session was meant to provide an exchange of information and experience on the following issues: Ethical Values; Actual Experiences of Fund Setting and Management; Uncertainties in Funding. At the end of each session time was allotted for a plenary discussion. The Rapporteur reviewed the main points and the lessons learnt at the end of the whole Topical Session. The Topical Session is documented as follows. A summary of the presentations, the country reports, the discussions and the key issues and lessons learnt is given in the main part of this report. The agenda of the Topical session can be found in Appendix 1 and the full papers supporting each presentation are given in Appendix 2. The national presentations on 'Actual experiences of Fund Setting and Management' in session 2 can be found in Appendix 3 and the national presentations on 'Uncertainties in Funding' in session 3 can be found in

  13. ASM observations of X-ray flares from 4U 0115+63 and ASM 1354-64.

    Science.gov (United States)

    Tsunemi, H.; Kitamoto, S.

    The authors report two X-ray flares detected with the All Sky Monitor (ASM) on board the GINGA satellite. One is from the recurrent X-ray pulsar 4U 0115+63 and the other is from the probable recurrent X-ray nova named ASM 1354-64. The maximum intensity for 4U 0115+63 was 180 mCrab and its duration was at least 22 days. Its spectrum was hard and resembled those of X-ray pulsars. The maximum intensity of ASM 1354-64 was 300 mCrab. It faded down below the detection limit at the end of August 1987. Its spectrum was soft and was similar to those of black hole candidates.

  14. Report on FY15 alloy 617 code rules development

    Energy Technology Data Exchange (ETDEWEB)

    Sham, Sam [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jetter, Robert I [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hollinger, Greg [Becht Engineering Co., Inc., Liberty Corner, NJ (United States); Pease, Derrick [Becht Engineering Co., Inc., Liberty Corner, NJ (United States); Carter, Peter [Stress Engineering Services, Inc., Houston, TX (United States); Pu, Chao [Univ. of Tennessee, Knoxville, TN (United States); Wang, Yanli [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-09-01

    Due to its strength at very high temperatures, up to 950°C (1742°F), Alloy 617 is the reference construction material for structural components that operate at or near the outlet temperature of the very high temperature gas-cooled reactors. However, the current rules in the ASME Section III, Division 5 Subsection HB, Subpart B for the evaluation of strain limits and creep-fatigue damage using simplified methods based on elastic analysis have been deemed inappropriate for Alloy 617 at temperatures above 650°C (1200°F) (Corum and Brass, Proceedings of ASME 1991 Pressure Vessels and Piping Conference, PVP-Vol. 215, p.147, ASME, NY, 1991). The rationale for this exclusion is that at higher temperatures it is not feasible to decouple plasticity and creep, which is the basis for the current simplified rules. This temperature, 650°C (1200°F), is well below the temperature range of interest for this material for the high temperature gas-cooled reactors and the very high temperature gas-cooled reactors. The only current alternative is, thus, a full inelastic analysis requiring sophisticated material models that have not yet been formulated and verified. To address these issues, proposed code rules have been developed which are based on the use of elastic-perfectly plastic (EPP) analysis methods applicable to very high temperatures. The proposed rules for strain limits and creep-fatigue evaluation were initially documented in the technical literature (Carter, Jetter and Sham, Proceedings of ASME 2012 Pressure Vessels and Piping Conference, papers PVP 2012 28082 and PVP 2012 28083, ASME, NY, 2012), and have been recently revised to incorporate comments and simplify their application. Background documents have been developed for these two code cases to support the ASME Code committee approval process. These background documents for the EPP strain limits and creep-fatigue code cases are documented in this report.

  15. Updating of ASME Nuclear Code Case N-201 to Accommodate the Needs of Metallic Core Support Structures for High Temperature Gas Cooled Reactors Currently in Development

    International Nuclear Information System (INIS)

    Basol, Mit; Kielb, John F.; MuHooly, John F.; Smit, Kobus

    2007-01-01

    On September 29, 2005, ASME Standards Technology, LLC (ASME ST-LLC) executed a multi-year, cooperative agreement with the United States DOE for the Generation IV Reactor Materials project. The project's objective is to update and expand appropriate materials, construction, and design codes for application in future Generation IV nuclear reactor systems that operate at elevated temperatures. Task 4 was embarked upon in recognition of the large quantity of ongoing reactor designs utilizing high temperature technology. Since Code Case N-201 had not seen a significant revision (except for a minor revision in September, 2006 to change the SA-336 forging reference for 304SS and 316SS to SA-965 in Tables 1.2(a) and 1.2(b), and some minor editorial changes) since December 1994, identifying recommended updates to support the current high temperature Core Support Structure (CSS) designs and potential new designs was important. As anticipated, the Task 4 effort identified a number of Code Case N-201 issues. Items requiring further consideration range from addressing apparent inconsistencies in definitions and certain material properties between CC-N-201 and Subsection NH, to inclusion of additional materials to provide the designer more flexibility of design. Task 4 developed a design parameter survey that requested input from the CSS designers of ongoing high temperature gas cooled reactor metallic core support designs. The responses to the survey provided Task 4 valuable input to identify the design operating parameters and future needs of the CSS designers. Types of materials, metal temperature, time of exposure, design pressure, design life, and fluence levels were included in the Task 4 survey responses. The results of the survey are included in this report. This research proves that additional work must be done to update Code Case N-201. Task 4 activities provide the framework for the Code Case N-201 update and future work to provide input on materials. Candidate

  16. Analysis of the ASME methodology for evaluation of erosion-corrosion defects with respect to the differences in the calculation and in materials used at the Dukovany NPP

    International Nuclear Information System (INIS)

    Kadecka, P.

    1995-01-01

    The problem of evaluation of tolerable defects and thinning of pipe walls was analyzed. In fact, a procedure for evaluation of tolerable defects is described in ASME Code Case N 480 based on the ASME ''Rules for Construction of Nuclear Power Plant Components''. The pipe systems of the Dukovany NPP, however, were constructed to different (East European) standards, and therefore caution should be exercised when applying US standards to this plant. The report demonstrates major differences between the ASME Standard and the proposed Czech standard ''A.S.I. Standards Documentation for Strength Calculations of Equipment and Piping of WWER Type Nuclear Power Plants'' developed by the Czech Association of Mechanical Engineers (A.S.I), evaluates the applicability of Code Case N 480 to the Dukovany plant, and proposes a Czech procedure for the evaluation. The basic characteristics of materials cited by ASME II and carbon steels used in the secondary circuit of the Dukovany NPP are also compared. (P.A.). 78 tabs., 2 figs., 4 refs

  17. Corporate governance in the Netherlands : an overview of the application of the Tabaksblat Code in 2004

    NARCIS (Netherlands)

    Akkermans, Dirk; van Ees, Hans; Hermes, Niels; Hooghiemstra, Reggy; van der Laan, Gerwin; Postma, Theo; van Witteloostuijn, Arjen

    2007-01-01

    This article examines the overall acceptance of the best practice provisions contained in the Dutch corporate governance code and identifies those that receive comparably less agreement among 150 Dutch listed companies in 2004. The findings indicate a high level of compliance with the Code.

  18. 46 CFR 56.60-1 - Acceptable materials and specifications (replaces 123 and Table 126.1 in ASME B31.1).

    Science.gov (United States)

    2010-10-01

    ... Fittings and Other Piping Components—Magnetic Particle Examination Method. SP-55 Quality Standard for Steel... certification, use is limited to applications within heat exchangers. 12 Hydrostatic testing of these fittings... and Seamless Wrought Steel Pipe. ASME B36.19M 2004 Stainless Steel Pipe. American Society for Testing...

  19. Comparison of design margin for core shroud in between design and construction code and fitness-for-service code

    International Nuclear Information System (INIS)

    Dozaki, Koji

    2007-01-01

    Structural design methods for core shroud of BWR are specified in JSME Design and Construction Code, like ASME Boiler and Pressure Vessel Code Sec. III, as a part of core support structure. Design margins are defined according to combination of the structural design method selected and service limit considered. Basically, those margins in JSME Code were determined after ASME Sec. III. Designers can select so-called twice-slope method for core shroud design among those design methods. On the other hand, flaw evaluation rules have been established for core shroud in JSME Fitness-for-Service Code. Twice-slope method is also adopted for fracture evaluation in that code even when the core shroud contains a flaw. Design margin was determined as structural factors separately from Design and Construction Code. As a natural consequence, there is a difference in those design margins between the two codes. In this paper, it is shown that the design margin in Fitness-for-Service Code is conservative by experimental evidences. Comparison of design margins between the two codes is discussed. (author)

  20. Index to place of publication of ASME Papers, 1978--1988

    International Nuclear Information System (INIS)

    Youngen, G.K.

    1990-06-01

    This index is a list of American Society of Mechanical Engineers (ASME) Papers that are reprinted in the ASME Transactions series of journals. ASME Papers are often cited only by their paper number, making it difficult to determine if the article has ever appeared in print in the journal literature. This index will be useful for tracking down those papers published as journal articles by the ASME. It will also serve as a guide for retention for subscribers to the ASME Papers and Transaction Series. Paper numbers that appear in the journals may be weeded from the collection of ASME Papers

  1. Applicability of ASME sections III and VIII and of B31.1 and B31.3 to DOE facilities

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1993-01-01

    DOE order 6430.1A Section 1300-3.2 requires that open-quotes....safety class items shall be designed to the ASME Boiler and Pressure Vessel Code (ASME Section III) or to other comparable safety-related codes and standards...close quotes. This requirement raises a host of technical and practical questions which, to the author's knowledge, have not been fully addressed in the past. This paper attempts to cover the following essential points, in order: Evolution of industry reference codes, Code scope, Safety margins, Logistical considerations, Costs, Backfit considerations. These points are covered in the context of a reference safety class piping and vessel system at a DOE facility which processes radioactive fluids, and which this paper calls the open-quotes reference DOE nuclear facilityclose quotes. In the conclusion, the author proposes three alternatives for code applicability which are ranked technically as open-quotes goodclose quotes, open-quotes closer to 6430.1Aclose quotes and open-quotes closest to 6430.1Aclose quotes. It is however questionable whether the alternatives which are labeled open-quotes closerclose quotes and open-quotes closestclose quotes are practically viable, as will be discussed

  2. Automatic examination of nuclear reactor vessels with focused search units. Status and typical application to inspections performed in accordance with ASME code

    International Nuclear Information System (INIS)

    Verger, B.; Saglio, R.

    1981-05-01

    The use of focused search units in nuclear reactor vessel examinations has significantly increased the capability of flaw indication detection and characterization. These search units especially allow a more accurate sizing of indications and a more efficient follow up of their history. In this aspect, they are a unique tool in the area of safety and reliability of installations. It was this type of search unit which was adopted to perform the examinations required within the scope of inservice inspections of all P.W.R. reactors of the French nuclear program. This paper summarizes the results gathered through the 4l examinations performed over the last five years. A typical application of focused search units in automated inspections performed in accordance with ASME code requirements on P.W.R. nuclear reactor vessels is then described

  3. Activated sludge model No. 2d, ASM2d

    DEFF Research Database (Denmark)

    Henze, M.

    1999-01-01

    The Activated Sludge Model No. 2d (ASM2d) presents a model for biological phosphorus removal with simultaneous nitrification-denitrification in activated sludge systems. ASM2d is based on ASM2 and is expanded to include the denitrifying activity of the phosphorus accumulating organisms (PAOs......). This extension of ASM2 allows for improved modeling of the processes, especially with respect to the dynamics of nitrate and phosphate. (C) 1999 IAWQ Published by Elsevier Science Ltd. All rights reserved....

  4. Low appendicular skeletal muscle mass (ASM) with limited mobility and poor health outcomes in middle-aged African Americans.

    Science.gov (United States)

    Malmstrom, Theodore K; Miller, Douglas K; Herning, Margaret M; Morley, John E

    2013-09-01

    Recent efforts to provide a consensus definition propose that sarcopenia be considered a clinical syndrome associated with the loss of both skeletal muscle mass and muscle function that occurs with aging. Validation of sarcopenia definitions that include both low muscle mass and poor muscle function is needed. In the population-based African American Health (AAH) study (N = 998 at baseline/wave 1), muscle mass and mobility were evaluated in a clinical testing center in a subsample of N = 319 persons (ages 52-68) at wave 4 (2004). Muscle mass was measured using dual energy x-ray absorptiometry and mobility by a 6-min walk test and 4-m gait walk test. Height corrected appendicular skeletal mass (ASM; 9.0 ± 1.5 in n = 124 males, 8.3 ± 2.2 in n = 195 females) was computed as total lean muscle mass in arms and legs (kilograms) divided by the square of height (meters). Cross-sectional and longitudinal (6-year) associations of low ASM (bottom 25 % AAH sample; ASM with limited mobility (4-m gait walk ≤1 m/s or 6-min walk ASM with limited mobility was associated with IADL difficulties (p = .008) and frailty (p = .040) but not with ADL difficulties or falls in cross-sectional analyses; and with ADL difficulties (p = .022), IADL difficulties (p = .006), frailty (p = .039), and mortality (p = .003) but not with falls in longitudinal analyses adjusted for age and gender. Low ASM alone was marginally associated with mortality (p = .085) but not with other outcomes in cross-sectional or longitudinal analyses. Low ASM with limited mobility is associated with poor health outcomes among late middle-aged African Americans.

  5. Safety Analysis Report for the KRI-ASM Transport Package

    Energy Technology Data Exchange (ETDEWEB)

    Bang, K. S.; Lee, J. C.; Kim, D. H.; Park, H. Y.; Kim, J. B.; Kim, H. J.; Seo, K. S

    2005-11-15

    Safety evaluation for the KRI-ASM transport package to transport safely I-131, which is produced at HANARO research reactor in KAERI, was carried out. In the safety analyses results for the KRI-ASM transport package, all the maximum stresses as well as the maximum temperature of the surface are lower than their allowable limits. The safety tests were performed by using the test model of the KRI-ASM transport package. Leak Test was performed after drop test and penetration test, the measured leakage rate was lower than allowable leakage rate. It is revealed that the containment integrity of the KRI-ASM transport package is maintained. Therefore, it shows that the integrity of the KRI-ASM transport package is well maintained.

  6. OM Code Requirements For MOVs -- OMN-1 and Appendix III

    Energy Technology Data Exchange (ETDEWEB)

    Kevin G. DeWall

    2011-08-01

    The purpose or scope of the ASME OM Code is to establish the requirements for pre-service and in-service testing of nuclear power plant components to assess their operational readiness. For MOVs this includes those that perform a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, and mitigating the consequences of an accident. This paper will present a brief history of industry and regulatory activities related to MOVs and the development of Code requirements to address weaknesses in earlier versions of the OM Code. The paper will discuss the MOV requirements contained in the 2009 version of ASME OM Code, specifically Mandatory Appendix III and OMN-1, Revision 1.

  7. OM Code Requirements For MOVs -- OMN-1 and Appendix III

    International Nuclear Information System (INIS)

    DeWall, Kevin G.

    2011-01-01

    The purpose or scope of the ASME OM Code is to establish the requirements for pre-service and in-service testing of nuclear power plant components to assess their operational readiness. For MOVs this includes those that perform a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, and mitigating the consequences of an accident. This paper will present a brief history of industry and regulatory activities related to MOVs and the development of Code requirements to address weaknesses in earlier versions of the OM Code. The paper will discuss the MOV requirements contained in the 2009 version of ASME OM Code, specifically Mandatory Appendix III and OMN-1, Revision 1.

  8. Proceedings of the Topical Sessions on Media Relations held in June 2004 and 2005

    International Nuclear Information System (INIS)

    2006-01-01

    An effective media strategy, including timely interaction with them is an indispensable tool for organisations or institutions involved in radioactive waste management. With this in mind, the Forum on Stakeholder Confidence (FSC) set up a Group on Communication and Outreach with a twofold objective: to assist FSC members in communicating with the radioactive waste management community, to assist FSC members in reaching a broader public. As part of this assignment, the Group organised two Topical Sessions on media strategy, in conjunction with the 2004 and 2005 FSC meetings. The main objective was to learn about the functioning of the media organisations, their structures and needs, with speakers chosen to represent the range of such media, as well as different countries and varying radioactive waste situations that may serve as illustrative examples, given the vast differences that may prevail between local, national, and international radioactive waste management situations and their treatment by the media. The sessions were attended by representatives of policy makers, regulators and implementers from the FSC organisations. The presentations and discussions illustrated current media strategies, best practices, successes and failures and lessons learn. These proceedings consist of a summary of the main points made by each speaker as well a collation of their papers

  9. Temporal Deductive Verification of Basic ASM Models

    OpenAIRE

    Daho, Hocine El-Habib; University of Oran; Benhamamouch, Djillali; University of Oran

    2010-01-01

    Abstract State Machines (ASMs, for short) provide a practical new computational model which has been applied in the area of software engineering for systems design and analysis. However, reasoning about ASM models occurs, not within a formal deductive system, but basically in the classical informal proofs style of mathematics. Several formal verification approaches for proving correctness of ASM models have been investigated. In this paper we consider the use of the TLA+logic for the deductive...

  10. Legal and economic implications of the German Craft Code Amendment 2004

    Directory of Open Access Journals (Sweden)

    Wolfgang Benzel

    2012-01-01

    Full Text Available As the main reason for initiating an amendment of the Trade and Crafts Code in 2004 was the decrease in the number of companies in general and the number of skilled crafts enterprises in particular and was also due to the fact that the number of employees in the skilled crafts sector had constantly fallen and many companies were not able to find a successor, it was the declared aim of the amendment to counter this structural crisis as well as reducing illegal employment and removing native discrimination. This would then ensure a higher level of employment especially through new company formations and takeovers of existing companies.In addition to providing an important contribution towards the assessment of the basic success of the 2004 Trade and Crafts Code amendment, the results can therefore be used at an international level for discussions on skilled crafts legislation outside Germany. As German skilled crafts legislation developed in a completely different manner from skilled crafts legislation in most other European countries, this aspect is particularly significant and it is conceivable that the results will be useful beyond the borders of the Federal Republic of Germany. The research findings will also be important in determining the limits of deregulation and when it can be considered counterproductive from an economic point of view.

  11. Present activity in ASME Section XI regarding risk-informed maintenance

    International Nuclear Information System (INIS)

    Hedden, Owen; Chockie, Alan

    2005-01-01

    Since 1996 Section XI of the ASME Boiler and Pressure Vessel Code has actively incorporated risk-informed concepts. The risk-informed process provides a framework for allocating inspection resources in a cost-effective manner and helps focus inspections where most critical for plant safety. Based on the success of the risk-informed ISI piping applications at US and non-US plants, Section XI has refined existing Code Cases and expanded the use of the risk-informed process to a variety of high-risk components and systems. The risk informed approach started in the area of inspection and is now being expanded to other plant maintenance activities. This article summarizes the Section XI actions and the continued development of the risk-informed process to improve nuclear plant maintenance. (author)

  12. Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.; Gwaltney, R.C.; Moore, S.E.

    1993-11-01

    This report collects and uses available data to reexamine the criteria for controlling primary loads in nuclear piping branch connections as expressed in Section III of the ASME Boiler and Pressure Vessel Code. In particular, the primary load stress indices given in NB-3650 and NB-3683 are reexamined. The report concludes that the present usage of the stress indices in the criteria equations should be continued. However, the complex treatment of combined branch and run moments is not supported by available information. Therefore, it is recommended that this combined loading evaluation procedure be replaced for primary loads by the separate leg evaluation procedure specified in NC/ND-3653.3(c) and NC/ND-3653.3(d). No recommendation is made for fatigue or secondary load evaluations for Class 1 piping. Further work should be done on the development of better criteria for treatment of combined branch and run moment effects

  13. Cisco ASM Router

    CERN Multimedia

    2001-01-01

    One of the two "ASM/2-32EM" boxes installed in 1988, from "Cisco Systems Inc." - then an unknown 20-employee company in Menlo Park, California (USA). This is one of the first two Cisco boxes to appear in Switzerland, and possibly Europe. The 220v power supply was a special modification made for use at CERN. They supported IP address filtering, which seemed just what CERN needed to help protect the new Cray XMP-48 super computer from network hackers. The two ASM boxes were both routers and terminal servers. They protected a secure private Ethernet segment used by the Cray project, as well as providing secure terminal connections to that segment, including CERN's first dialback terminal service, which allowed Cray and CERN system analysts to work on the machine from home, using another Cisco feature called TACACS. (Kindly offered by B. Segal who discovered this company while at a Usenix Conference in Phoenix, Arizona in June 1987.)

  14. Regulation of dynein-mediated autophagosomes trafficking by ASM in CASMCs.

    Science.gov (United States)

    Xu, Ming; Zhang, Qiufang; Li, Pin-Lan; Nguyen, Thaison; Li, Xiang; Zhang, Yang

    2016-01-01

    Acid sphingomyelinase (ASM; gene symbol Smpd1) has been shown to play a crucial role in autophagy maturation by controlling lysosomal fusion with autophagosomes in coronary arterial smooth muscle cells (CASMCs). However, the underlying molecular mechanism by which ASM controls autophagolysosomal fusion remains unknown. In primary cultured CASMCs, lysosomal Ca2+ induced by 7-ketocholesterol (7-Ket, an atherogenic stimulus and autophagy inducer) was markedly attenuated by ASM deficiency or TRPML1 gene silencing suggesting that ASM signaling is required for TRPML1 channel activity and subsequent lysosomal Ca(2+) release. In these CASMCs, ASM deficiency or TRPML1 gene silencing markedly inhibited 7-Ket-induced dynein activation. In addition, 7-Ket-induced autophagosome trafficking, an event associated with lysosomal Ca(2+) release and dynein activity, was significantly inhibited in ASM-deficient (Smpd1(-/-)) CASMCs compared to that in Smpd1(+/+) CASMCs. Finally, overexpression of TRPML1 proteins restored 7-Ket-induced lysosomal Ca(2+) release and autophagosome trafficking in Smpd1-/- CASMCs. Collectively, these results suggest that ASM plays a critical role in regulating lysosomal TRPML1-Ca(2+) signaling and subsequent dynein-mediated autophagosome trafficking, which leads its role in controlling autophagy maturation in CASMCs under atherogenic stimulation.

  15. Storage Tanks - Selection Of Type, Design Code And Tank Sizing

    International Nuclear Information System (INIS)

    Shatla, M.N; El Hady, M.

    2004-01-01

    The present work gives an insight into the proper selection of type, design code and sizing of storage tanks used in the Petroleum and Process industries. In this work, storage tanks are classified based on their design conditions. Suitable design codes and their limitations are discussed for each tank type. The option of storage under high pressure and ambient temperature, in spherical and cigar tanks, is compared to the option of storage under low temperature and slight pressure (close to ambient) in low temperature and cryogenic tanks. The discussion is extended to the types of low temperature and cryogenic tanks and recommendations are given to select their types. A study of pressurized tanks designed according to ASME code, conducted in the present work, reveals that tanks designed according to ASME Section VIII DIV 2 provides cost savings over tanks designed according to ASME Section VIII DlV 1. The present work is extended to discuss the parameters that affect sizing of flat bottom cylindrical tanks. The analysis shows the effect of height-to-diameter ratio on tank instability and foundation loads

  16. Code boiler and pressure vessel life assessment

    International Nuclear Information System (INIS)

    Farr, J.R.

    1992-01-01

    In the United States of America and in Canada, laws and controls for determining life assessment for continued operation of equipment exist only for those pressure vessels built to Section III and evaluated according to Section XI. In this presentation, some of those considerations which are made in the USA and Canada for deciding on life or condition assessment of boilers and pressure vessels designed and constructed to other sections of the ASME Boiler and Pressure Vessel Code are reviewed. Life assessment or condition assesssment is essential in determining what is necessary for continued operation. With no ASME rules being adopted by laws or regulations, other than OSHA in the USA and similar environmental controls in Canada, to control life assessment for continued operation, the equipment owner must decide if assessment is to be done and how much to do. Some of those considerations are reviewed along with methods and procedures to make an assessment along with a discussion of where the ASME B and PV Code currently stands regarding continued operation. (orig.)

  17. High temperature structural integrity evaluation method and application studies by ASME-NH for the next generation reactor design

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, Jae Han

    2006-01-01

    The main purpose of this paper is to establish the high temperature structural integrity evaluating procedures for the next generation reactors, which are to be operated at over 500 .deg. C and for 60 years. To do this, comparison studies of the high temperature structural design codes and assessment procedures such as the ASME-NH (USA), RCC-MR (France), DDS (Japan), and R5 (UK) are carried out in view of the accumulated inelastic strain and the creep-fatigue damage evaluations. Also the application procedures of the ASME-NH rules with the actual thermal and structural analysis results are described in detail. To overcome the complexity and the engineering costs arising from a real application of the ASME-NH rules by hand, all the procedures established in this study such as the time-dependent primary stress limits, total accumulated creep ratcheting strain limits, and the creep-fatigue damage limits are computerized and implemented into the SIE ASME-NH program. Using this program, the selected high temperature structures subjected to two cycle types are evaluated and the parametric studies for the effects of the time step size, primary load, number of cycles, normal temperature for the creep damage evaluations and the effects of the load history on the creep ratcheting strain calculations are investigated

  18. AsmL Specification of a Ptolemy II Scheduler

    DEFF Research Database (Denmark)

    Lázaro Cuadrado, Daniel; Koch, Peter; Ravn, Anders Peter

    2003-01-01

    Ptolemy II is a tool that combines different computational models for simulation and design of embedded systems. AsmL is a software specification language based on the Abstract State Machine formalism. This paper reports on development of an AsmL model of the Synchronous Dataflow domain scheduler...

  19. CEASEMT system: the TEDEL code. Pipings - Plasticity - Dynamics - Statics - Buckling - Thermoplasticity - Creep - Large displacements - FLUIDS - SEISMS - ASME

    International Nuclear Information System (INIS)

    Hoffmann, Alain; Jeanpierre, Francoise; Axisa, Francois; Chevalier, Gerard; Lepareux, Michel.

    1977-01-01

    The TEDEL code is intended for elastic and plastic computation of three-dimensional pipes and frames with possible junction to shells. The structures are described with using assemblies of beam elements, or piping elements such as, curved pipes, 90 0 elbows, tees, any elements, the stiffness properties of which are given to TEDEL. TEDEL allows the dynamic computation of the structures: search of eigenfrequencies and eigenmodes of vibration, time response to any time-dependent canvassing. This response can be obtained either from recombining a number of eigenmodes, or from a direct numerical integration of the dynamics equation. In these last two cases TEDEL accounts for some possible damping. A TEDEL option allows critical buckling loads to be computed (Euler). The structures can offer any shapes comprising any number of materials. The data are readout without any format, and distributed in optional commands with a precise physical meaning: GEOMETRY, MATERIALS, LOAD, COMPUTATION, END. A dynamical memory control allows the size of the routine to be adapted to the problem to be treated. For pipings, an option is intended for an automatic checking of the stress level with regard to the limiting values of the ASME. Geometrical data, node positions, element numbering are given by COCO which also delivers perspective drawings for the structure to be studied. The results on magnetic tapes can be treated by the subroutines ESPACE-VISU-TEMPS [fr

  20. Comparison of Fatigue crack growth rate of Type 347 stainless steel with ASME and JSME models

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Seokmin; Min, Ki-Deuk; Jeon, Soon-Hyeok; Lee, Bong-Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this study, the FCGR of 347SS was evaluated in modified PWR high temperature water conditions. The FCGRs of 347SS under modified pressurized-water conditions were measured by using compact-tension (CT) specimens at different levels of dissolved oxygen (DO), and it were compared with other models proposed by ASME and Japanese groups. Corrosion fatigue is main factor of environmental fatigue effect. Increase of DO level in water induced more corrosion damage, and it accelerated FCGR in PWR and FCGR of 347SS in PWR water condition was faster than reference curves in J-PWR and ASME draft code case derived by 304 and 316 stainless steel, but it was slower than J-BWR reference curve. Using J-BWR model for estimating the FCGR of 347SS under PWR might be conservative.

  1. Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility according to ASME-NH and RCC-MRx Codes

    International Nuclear Information System (INIS)

    Lim, Dong-Won; Lee, Hyeong-Yeon; Eoh, Jae-Hyuk; Son, Seok-Kwon; Kim, Jong-Bum; Jeong, Ji-Young

    2016-01-01

    The objective of the STELLA-2 is to support the specific design approval for PGSFR by synthetic reviews of key safety issues and code validations through the integral effect tests. Due to its high temperature operation in SFRs (and in a testing facility) up to 550 °C, thermally induced creep-fatigue damage is very likely in components including a reactor vessel, reactor internals (interior structures), heat exchangers, pipelines, etc. In this study, structural integrity of the components such as reactor vessel and internals in STELLA-2 has been evaluated against creep-fatigue failures at a concept-design step. As 2D analysis yields far conservative results, a realistic 3D simulation is performed by a commercial software. A design integrity guarding against a creep-fatigue damage failure operating at high temperature was evaluated for the reactor vessel with its internal structure of the STELLA-2. Both the high temperature design codes were used for the evaluation, and results were compared. All the results showed the vessel as a whole is safely designed at the given operating conditions, while the ASME-NH gives a conservative evaluation

  2. Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility according to ASME-NH and RCC-MRx Codes

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Dong-Won; Lee, Hyeong-Yeon; Eoh, Jae-Hyuk; Son, Seok-Kwon; Kim, Jong-Bum; Jeong, Ji-Young [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    The objective of the STELLA-2 is to support the specific design approval for PGSFR by synthetic reviews of key safety issues and code validations through the integral effect tests. Due to its high temperature operation in SFRs (and in a testing facility) up to 550 °C, thermally induced creep-fatigue damage is very likely in components including a reactor vessel, reactor internals (interior structures), heat exchangers, pipelines, etc. In this study, structural integrity of the components such as reactor vessel and internals in STELLA-2 has been evaluated against creep-fatigue failures at a concept-design step. As 2D analysis yields far conservative results, a realistic 3D simulation is performed by a commercial software. A design integrity guarding against a creep-fatigue damage failure operating at high temperature was evaluated for the reactor vessel with its internal structure of the STELLA-2. Both the high temperature design codes were used for the evaluation, and results were compared. All the results showed the vessel as a whole is safely designed at the given operating conditions, while the ASME-NH gives a conservative evaluation.

  3. Assessment of crack-like flaws - Comparison of procedures in BS 7910, API 579-1/ASME FFS-1, RSE-M AND FITNET

    International Nuclear Information System (INIS)

    Chaudouet, A.

    2007-01-01

    Among all Fitness For Service Codes enabling to assess flaws in metallic structures and to evaluate their remaining life, new editions of the most important ones at the international level have been issued recently. The latest edition of BS 7910 in United Kingdom has been released in October 2005. In the USA, API and ASME have edited a new standard in 2007, API579-1/ASME FFS-1, dedicated to pressure equipment. In France, the rules concerning the of Light Water Reactors, RSE-M, have been updated in 2005. Finally, in Europe, the FITNET network is writing a document based on BS 7910 but extended with the most recent results in this domain. Rules given in these documents to assess crack-like flaws with respect to fracture and fatigue propagation are presented. They are compared in order to point out the most interesting aspects of each ones and to identify those which could be generalized. An example assessed with the above mentioned 'Codes' enlightens the differences in the results with respect to the 'Code' used. (author) [fr

  4. ASME stress linearization and classification - a discussion based on a case study

    International Nuclear Information System (INIS)

    Miranda, Carlos A. de J.; Faloppa, Altair A.; Mattar Neto, Miguel; Fainer, Gerson

    2011-01-01

    The ASME code, specially in its Nuclear Division (Subsection NB - Class I Components), gives some recommendations to the structural analyst on how to perform the verifications required to prove the design as good as the by-analysis prevented failures modes. Each of these failure modes has specific stress limits which are established based on simple but conservative hypothesis like the material perfectly plastic behavior and the shell theory with its typical membrane and bending stresses with linear distribution along the thickness. Other detail to keep in mind is the code distinction between primary and secondary stresses (respectively, stress that came due to equilibrium and due to displacement compatibility). In general, the numerical models used in the analyses are developed with plane or 3D solid elements and due this fact no direct comparison with the code limits can be done and, besides that, the programs do not distinguish between primary and secondary stresses. Mostly, the later are produced due to the temperature variation but they also appear near discontinuities. Sometimes, this classification is not so clear or direct. To perform the required ASME Code verifications the analyst should obtain the membrane and bending stresses from the plane or 3-D model which is called stress linearization and, also, should classify them as primary and secondary. (The excess between the maximum stress at a point and the sum of these linearized values is called peak stress and is included in the fatigue verification.) This task, most of the time is not a simple one due to the nature of the involved load and/or the complex geometry under analysis. In fact, there are several studies discussing on how to perform these stress classification and linearization. The present paper shows a discussion on how to perform these verifications based on a generic geometry found in many plants, from petrochemical to nuclear, which emphasizes some of theses issues. (author)

  5. ASME stress linearization and classification - a discussion based on a case study

    Energy Technology Data Exchange (ETDEWEB)

    Miranda, Carlos A. de J.; Faloppa, Altair A.; Mattar Neto, Miguel; Fainer, Gerson, E-mail: cmiranda@ipen.b, E-mail: afaloppa@ipen.b, E-mail: mmattar@ipen.b, E-mail: gfainer@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The ASME code, specially in its Nuclear Division (Subsection NB - Class I Components), gives some recommendations to the structural analyst on how to perform the verifications required to prove the design as good as the by-analysis prevented failures modes. Each of these failure modes has specific stress limits which are established based on simple but conservative hypothesis like the material perfectly plastic behavior and the shell theory with its typical membrane and bending stresses with linear distribution along the thickness. Other detail to keep in mind is the code distinction between primary and secondary stresses (respectively, stress that came due to equilibrium and due to displacement compatibility). In general, the numerical models used in the analyses are developed with plane or 3D solid elements and due this fact no direct comparison with the code limits can be done and, besides that, the programs do not distinguish between primary and secondary stresses. Mostly, the later are produced due to the temperature variation but they also appear near discontinuities. Sometimes, this classification is not so clear or direct. To perform the required ASME Code verifications the analyst should obtain the membrane and bending stresses from the plane or 3-D model which is called stress linearization and, also, should classify them as primary and secondary. (The excess between the maximum stress at a point and the sum of these linearized values is called peak stress and is included in the fatigue verification.) This task, most of the time is not a simple one due to the nature of the involved load and/or the complex geometry under analysis. In fact, there are several studies discussing on how to perform these stress classification and linearization. The present paper shows a discussion on how to perform these verifications based on a generic geometry found in many plants, from petrochemical to nuclear, which emphasizes some of theses issues. (author)

  6. Organizing by covenant : the organization of transitional labor markets : paper IREC Conference 2004 'Governance issues in shifting industrial and employment relations' Utrecht, The Netherlands, August 26-28, 2004 : session potential and limits of national level socio-economic governance

    NARCIS (Netherlands)

    Korver, T.; Oeij, P.R.A.

    2004-01-01

    From 26-28 August 2004 in Utrecht the Industrial Relations in Europe Conference (IREC) was held on governance issues in shifting industrial and employment relations. As part of the session 'potential and limits of national level socio-economic governance' this paper about the organization of

  7. Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

    International Nuclear Information System (INIS)

    Fish, J.F.

    1979-01-01

    Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

  8. Penetration of ASM 981 in canine skin: a comparative study.

    Science.gov (United States)

    Gutzwiller, Meret E Ricklin; Reist, Martin; Persohn, Elke; Peel, John E; Roosje, Petra J

    2006-01-01

    ASM 981 has been developed for topical treatment of inflammatory skin diseases. It specifically inhibits the production and release of pro-inflammatory cytokines. We measured the skin penetration of ASM 981 in canine skin and compared penetration in living and frozen skin. To make penetration of ASM 981 visible in dog skin, tritium labelled ASM 981 was applied to a living dog and to defrosted skin of the same dog. Using qualitative autoradiography the radioactive molecules were detected in the lumen of the hair follicles until the infundibulum, around the superficial parts of the hair follicles and into a depth of the dermis of 200 to 500 microm. Activity could not be found in deeper parts of the hair follicles, the dermis or in the sebaceous glands. Penetration of ASM 981 is low in canine skin and is only equally spread in the upper third of the dermis 24 hours after application. Penetration in frozen skin takes even longer than in living canine skin but shows the same distribution.

  9. Interim status report on the revision of ASME PTC 12.1 -- closed feedwater heaters

    International Nuclear Information System (INIS)

    Stellern, J.L.; Hoobler, J.V.; Milton, J.W.; Welch, T.; Kona, C.; Thompson, H.N.; Tsou, J.L.

    1993-01-01

    The ASME Performance Test Code (PTC) 12.1-1978 for the performance testing of feedwater heaters is being revised extensively and updated. The committee anticipates that the final draft of the proposed Code will be ready for industry review in 1993. This Code revision will greatly enhance the usefulness and cost effectiveness of feedwater heater performance testing. This paper has been prepared to report on the progress of the committee and to disseminate information on the nature of the revision. Included in this paper are some of the notable changes intended for the Code. The most extensive change is the calculation method, which is described in step-by-step detail. An approach is also described for using ultrasonic flow techniques to test individual or split-string feedwater heaters, when flow nozzles are not available. Additionally some educational information on the use and limitations of ultrasonic measurement instrumentation is included. Discussion is also included on the required uncertainty analysis. 3 refs., 2 figs., 2 tabs

  10. Statistical analysis of the ASME KIc database

    International Nuclear Information System (INIS)

    Sokolov, M.A.

    1998-01-01

    The American Society of Mechanical Engineers (ASME) K Ic curve is a function of test temperature (T) normalized to a reference nil-ductility temperature, RT NDT , namely, T-RT NDT . It was constructed as the lower boundary to the available K Ic database. Being a lower bound to the unique but limited database, the ASME K Ic curve concept does not discuss probability matters. However, a continuing evolution of fracture mechanics advances has led to employment of the Weibull distribution function to model the scatter of fracture toughness values in the transition range. The Weibull statistic/master curve approach was applied to analyze the current ASME K Ic database. It is shown that the Weibull distribution function models the scatter in K Ic data from different materials very well, while the temperature dependence is described by the master curve. Probabilistic-based tolerance-bound curves are suggested to describe lower-bound K Ic values

  11. Code on nuclear air and gas treatment ASME/ANSI AG-1

    International Nuclear Information System (INIS)

    Miller, W.H. Jr.

    1993-01-01

    The focus of this panel is on equipment code section work over the past two years. Major topics include changes in Filter Code Sections, revamping of the Ductwork Code Section, and emergence of an improved I ampersand C Code Section. Actual applications of AG-1 are to be discussed by CONAGT members. Remaining time will be devoted to fielding questions concerning ASMA/ANSI AG-1

  12. Monte Carlo Codes Invited Session

    International Nuclear Information System (INIS)

    Trama, J.C.; Malvagi, F.; Brown, F.

    2013-01-01

    This document lists 22 Monte Carlo codes used in radiation transport applications throughout the world. For each code the names of the organization and country and/or place are given. We have the following computer codes. 1) ARCHER, USA, RPI; 2) COG11, USA, LLNL; 3) DIANE, France, CEA/DAM Bruyeres; 4) FLUKA, Italy and CERN, INFN and CERN; 5) GEANT4, International GEANT4 collaboration; 6) KENO and MONACO (SCALE), USA, ORNL; 7) MC21, USA, KAPL and Bettis; 8) MCATK, USA, LANL; 9) MCCARD, South Korea, Seoul National University; 10) MCNP6, USA, LANL; 11) MCU, Russia, Kurchatov Institute; 12) MONK and MCBEND, United Kingdom, AMEC; 13) MORET5, France, IRSN Fontenay-aux-Roses; 14) MVP2, Japan, JAEA; 15) OPENMC, USA, MIT; 16) PENELOPE, Spain, Barcelona University; 17) PHITS, Japan, JAEA; 18) PRIZMA, Russia, VNIITF; 19) RMC, China, Tsinghua University; 20) SERPENT, Finland, VTT; 21) SUPERMONTECARLO, China, CAS INEST FDS Team Hefei; and 22) TRIPOLI-4, France, CEA Saclay

  13. The statistical background to proposed ASME/MPC fracture toughness reference curves

    International Nuclear Information System (INIS)

    Oldfield, W.

    1981-01-01

    The ASME Pressure Vessel Codes define, in Sec. 11, lower bound fracture toughness curves. These curves are used to predict the lower bound fracture toughness on the basis of the RT test procedure. This test is used to remove heat to heat differences, by permitting the lower bound (reference) curve to be moved along the temperature scale according to the measured RT. Numerous objections have been raised to the procedure, and a Subcommittee (the ASME/MPC Working Group on Reference Toughness) is currently revising the codified procedures for fracture toughness prediction. The task has required a substantial amount of statistical work, since the new procedure are to have a statistical basis. Using initiation fracture toughness (J-Integral R curve procedures in the ductile domain) it was shown that when CVN energy data is properly transformed it is highly correlated with valid fracture toughness measurements. A single functional relationship can be used to predict the mean fracture toughness for a sample of steel from a set of CVN energy measurements, and the coefficients of the function tabulated. More importantly, the approximate lower statistical bounds to the initiation fracture toughness behaviour can be similarly predicted, and coefficients for selected bounds have also been tabulated. (orig.)

  14. Flanged joints with contact outside the bolt circle: ASME Part B design rules

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.; Moore, S.E.

    1976-05-01

    The ASME Boiler and Pressure Vessel Code, Section VIII, Division 1, gives rules which are subdivided into ''Part A'' and ''Part B''. Part A covers flanged joints where contact between flanges occurs through a gasket located inside the bolt holes. Part B covers flanged joints with contact outside the bolt holes. This report (a) summarizes the theory for Part B flanged joints, (b) presents examples which show the significant differences between Part A flanged joints and Part B flanged joints, (c) presents the available test data relevant to the characteristics of Part B flanged joints, (d) gives listings of two computer programs which can be used to evaluate the characteristics of Part B flanged joints, and (e) gives recommendations for Code revisions and other aspects of Part B flanged-joint design

  15. Equilíbrio corporal em crianças e adolescentes asmáticos e não asmáticos

    Directory of Open Access Journals (Sweden)

    Marta Cristina Rodrigues da Silva

    2013-06-01

    Full Text Available O objetivo foi analisar e comparar o equilíbrio corporal em crianças e adolescentes asmáticos e não asmáticos. Fizeram parte do grupo de estudos 24 sujeitos com idades de 7 a 14 anos divididos em dois grupos: grupo asmático e grupo controle. Para avaliação do equilíbrio corporal utilizou-se uma plataforma de força. Foram utilizadas as condições, olhos abertos e fechados com três tentativas aleatórias, com duração de 30 segundos cada uma. Os resultados apontaram diferença significativa entre os grupos, no teste de equilíbrio com olhos abertos apresentando maior amplitude de deslocamento na direção ântero-posterior (COPap (p = 0,04, e médio lateral (COPml (p = 0,02 no grupo asmático. Enquanto que no teste com olhos fechados a diferença foi significante apenas na amplitude de deslocamento ântero-posterior (COPap (p = 0,02 e Área de Elipse (p=0,03. Desse modo, a asma com suas limitações e consequências parece influenciar negativamente no equilíbrio corporal de seus portadores quando comparados com crianças sem a patologia e da mesma faixa etária.

  16. Structural analysis program of plant piping system. Introduction of AutoPIPE V8i new feature. JSME PPC-class 2 piping code

    International Nuclear Information System (INIS)

    Motohashi, Kazuhiko

    2009-01-01

    After an integration with ADLPipe, AutoPIPE V8i (ver.9.1) became the structural analysis program of plant piping system featured with analysis capability for the ASME NB Class 1 and JSME PPC-Class 2 piping codes including ASME NC Class 2 and ASME ND Class 3. This article described analysis capability for the JSME PPC-Class 2 piping code as well as new general features such as static analysis up to 100 thermal, 10 seismic and 10 wind load cases including different loading scenarios and pipe segment edit function: join, split, reverse and re-order segments. (T. Tanaka)

  17. SDZ ASM 981: an emerging safe and effective treatment for atopic dermatitis.

    Science.gov (United States)

    Luger, T; Van Leent, E J; Graeber, M; Hedgecock, S; Thurston, M; Kandra, A; Berth-Jones, J; Bjerke, J; Christophers, E; Knop, J; Knulst, A C; Morren, M; Morris, A; Reitamo, S; Roed-Petersen, J; Schoepf, E; Thestrup-Pedersen, K; Van Der Valk, P G; Bos, J D

    2001-04-01

    SDZ ASM 981 is a selective inhibitor of the production of pro-inflammatory cytokines from T cells and mast cells in vitro. It is the first ascomycin macrolactam derivative under development for the treatment of inflammatory skin diseases. This study was designed to determine the safety and efficacy of SDZ ASM 981 cream at concentrations of 0.05%, 0.2%, 0.6% and 1.0% in the treatment of patients with atopic dermatitis and to select the concentration to be used in phase III studies. This was a double-blind, randomized, parallel-group, multicentre dose-finding study. A total of 260 patients were randomly assigned to treatment with SDZ ASM 981 cream at concentrations of 0.05%, 0.2%, 0.6%, or 1.0%, matching vehicle cream, or the internal control 0.1% betamethasone-17-valerate cream (BMV). Treatment was given twice daily for up to 3 weeks. A clear dose-response relationship for SDZ ASM 981 was evident, with 0.2%, 0.6% and 1.0% SDZ ASM 981 creams all being significantly more effective than vehicle (P = 0.041, 0.001 and 0.008, respectively) in terms of baseline to end-point changes in the Eczema Area Severity Index (EASI) and pruritus score. The 1.0% cream was the most effective SDZ ASM 981 concentration. BMV was more effective than the SDZ ASM 981 creams tested in this study. It appears that the efficacy plateau was not reached with the SDZ ASM 981 creams within 3 weeks treatment. SDZ ASM 981 was well tolerated. Burning or a feeling of warmth were the only adverse events reported more frequently in the 0.6% and 1.0% SDZ ASM 981 treatment groups than in the vehicle treatment group (42.9%, 48.9% and 34.9%, respectively). Few systemic adverse events were reported during the study (headache was the most frequent systemic event reported by 15 of 252 patients) and none was considered to be related to treatment. The local tolerability profile of the 1.0% cream was similar to that of the lower concentrations. 1.0% SDZ ASM 981 cream, which was shown to be safe, well tolerated and

  18. Code Team Training: Demonstrating Adherence to AHA Guidelines During Pediatric Code Blue Activations.

    Science.gov (United States)

    Stewart, Claire; Shoemaker, Jamie; Keller-Smith, Rachel; Edmunds, Katherine; Davis, Andrew; Tegtmeyer, Ken

    2017-10-16

    Pediatric code blue activations are infrequent events with a high mortality rate despite the best effort of code teams. The best method for training these code teams is debatable; however, it is clear that training is needed to assure adherence to American Heart Association (AHA) Resuscitation Guidelines and to prevent the decay that invariably occurs after Pediatric Advanced Life Support training. The objectives of this project were to train a multidisciplinary, multidepartmental code team and to measure this team's adherence to AHA guidelines during code simulation. Multidisciplinary code team training sessions were held using high-fidelity, in situ simulation. Sessions were held several times per month. Each session was filmed and reviewed for adherence to 5 AHA guidelines: chest compression rate, ventilation rate, chest compression fraction, use of a backboard, and use of a team leader. After the first study period, modifications were made to the code team including implementation of just-in-time training and alteration of the compression team. Thirty-eight sessions were completed, with 31 eligible for video analysis. During the first study period, 1 session adhered to all AHA guidelines. During the second study period, after alteration of the code team and implementation of just-in-time training, no sessions adhered to all AHA guidelines; however, there was an improvement in percentage of sessions adhering to ventilation rate and chest compression rate and an improvement in median ventilation rate. We present a method for training a large code team drawn from multiple hospital departments and a method of assessing code team performance. Despite subjective improvement in code team positioning, communication, and role completion and some improvement in ventilation rate and chest compression rate, we failed to consistently demonstrate improvement in adherence to all guidelines.

  19. Effect of Inter-sentential vs Intra-sentential Code-Switching: With a Focus on Past Tense

    Directory of Open Access Journals (Sweden)

    Hanieh Kashi

    2018-03-01

    Full Text Available The current study aimed at the comparative effect of inter-sentential vs intra-sentential code-switching on learning past tense. Initially, through non-random convenient sampling, the researcher chose 90 female EFL learners at the elementary level. Next, Key English Test (KET was administered to the 90 learners and the results were used to select 60 participants for the purpose of this study. The participants were then divided into two groups each consisting of 30 learners. Afterwards, a grammar pretest having 30 items focusing on past simple tense was given to both groups. Following that, the grammatical explanations were provided for the two groups for ten sessions using code-switching.  The first experimental group received inter-sentential code switching in line with Reyes’s (2004 as a switch between two languages, where a sentence in one of the languages is completed and the next sentence starts with the other language (Reyes, 2004. In the second experimental group, in line with Reyes’s (2004, the switching occurred within a sentence. The results of statistical analysis indicated that inter-sentential code-switching proved more effective compared to intra-sentential code-switching on the learning of past tense by EFL learners. Based on the findings of the present study, EFL teachers are encouraged to use inter-sentential code-switching more compared to intra-sentential code-switching when it comes to teaching grammar.

  20. GC-ASM: Synergistic Integration of Graph-Cut and Active Shape Model Strategies for Medical Image Segmentation.

    Science.gov (United States)

    Chen, Xinjian; Udupa, Jayaram K; Alavi, Abass; Torigian, Drew A

    2013-05-01

    Image segmentation methods may be classified into two categories: purely image based and model based. Each of these two classes has its own advantages and disadvantages. In this paper, we propose a novel synergistic combination of the image based graph-cut (GC) method with the model based ASM method to arrive at the GC-ASM method for medical image segmentation. A multi-object GC cost function is proposed which effectively integrates the ASM shape information into the GC framework. The proposed method consists of two phases: model building and segmentation. In the model building phase, the ASM model is built and the parameters of the GC are estimated. The segmentation phase consists of two main steps: initialization (recognition) and delineation. For initialization, an automatic method is proposed which estimates the pose (translation, orientation, and scale) of the model, and obtains a rough segmentation result which also provides the shape information for the GC method. For delineation, an iterative GC-ASM algorithm is proposed which performs finer delineation based on the initialization results. The proposed methods are implemented to operate on 2D images and evaluated on clinical chest CT, abdominal CT, and foot MRI data sets. The results show the following: (a) An overall delineation accuracy of TPVF > 96%, FPVF ASM for different objects, modalities, and body regions. (b) GC-ASM improves over ASM in its accuracy and precision to search region. (c) GC-ASM requires far fewer landmarks (about 1/3 of ASM) than ASM. (d) GC-ASM achieves full automation in the segmentation step compared to GC which requires seed specification and improves on the accuracy of GC. (e) One disadvantage of GC-ASM is its increased computational expense owing to the iterative nature of the algorithm.

  1. ASME method for particle reconstruction

    International Nuclear Information System (INIS)

    Ierusalimov, A.P.

    2009-01-01

    The method of approximate solution of motion equation (ASME) was used to reconstruct the parameters for charged particles. It provides a good precision for momentum, angular and space parameters of particles in coordinate detectors. The application of the method for CBM, HADES and MPD/NICA setups is discussed

  2. Integrin and GPCR Crosstalk in the Regulation of ASM Contraction Signaling in Asthma.

    Science.gov (United States)

    Teoh, Chun Ming; Tam, John Kit Chung; Tran, Thai

    2012-01-01

    Airway hyperresponsiveness (AHR) is one of the cardinal features of asthma. Contraction of airway smooth muscle (ASM) cells that line the airway wall is thought to influence aspects of AHR, resulting in excessive narrowing or occlusion of the airway. ASM contraction is primarily controlled by agonists that bind G protein-coupled receptor (GPCR), which are expressed on ASM. Integrins also play a role in regulating ASM contraction signaling. As therapies for asthma are based on symptom relief, better understanding of the crosstalk between GPCRs and integrins holds good promise for the design of more effective therapies that target the underlying cellular and molecular mechanism that governs AHR. In this paper, we will review current knowledge about integrins and GPCRs in their regulation of ASM contraction signaling and discuss the emerging concept of crosstalk between the two and the implication of this crosstalk on the development of agents that target AHR.

  3. CERN Technical Training 2004: New Short Courses (SC) on Microsoft Outlook

    CERN Multimedia

    Monique Duval

    2004-01-01

    The CERN Technical Training programme is now proposing a new format for courses on Microsoft Outlook. Three two-hours Short Courses (SC) will cover basic and advanced functionalities of the recommended mail client for email at CERN. Each module can be followed independently. The next scheduled sessions will take place as follows: Outlook (SC I): E-mail. Next session: 22.10.2004 (9h00-11h00) Outlook (SC II): Calendar, Tasks and Notes. Next session: 22.10.2004 (14h00-16h00) Outlook (SC III): Meetings and Delegation. Next session: 9.11.2004 (14h00-16h00) In particular, SC I will cover how to open, create and send email, work with attachments, use stationery, organise mail, and work with the address book, SC II will show how to work with the calendar, tasks and notes, and SC III will cover how to organise and manage meetings, work with meeting requests, share tasks, and use email and calendar delegation. The number of participants to each session is limited to 8. The instructor is English-French bilingual, and...

  4. Inhibition of allergen-induced basophil activation by ASM-024, a nicotinic receptor ligand.

    Science.gov (United States)

    Watson, Brittany M; Oliveria, John Paul; Nusca, Graeme M; Smith, Steven G; Beaudin, Sue; Dua, Benny; Watson, Rick M; Assayag, Evelynne Israël; Cormier, Yvon F; Sehmi, Roma; Gauvreau, Gail M

    2014-01-01

    Nicotinic acetylcholine receptors (nAChRs) were identified on eosinophils and shown to regulate inflammatory responses, but nAChR expression on basophils has not been explored yet. We investigated surface receptor expression of nAChR α4, α7 and α1/α3/α5 subunits on basophils. Furthermore, we examined the effects of ASM-024, a synthetic nicotinic ligand, on in vitro anti-IgE and in vivo allergen-induced basophil activation. Basophils were enriched from the peripheral blood of allergic donors and the expression of nAChR subunits and muscarinic receptors was determined. Purified basophils were stimulated with anti-IgE in the presence of ASM-024 with or without muscarinic or nicotinic antagonists for the measurement of CD203c expression and histamine release. The effect of 9 days of treatment with 50 and 200 mg ASM-024 on basophil CD203c expression was examined in the blood of mild allergic asthmatics before and after allergen inhalation challenge. nAChR α4, α7 and α1/α3/α5 receptor subunit expression was detected on basophils. Stimulation of basophils with anti-IgE increased CD203c expression and histamine release, which was inhibited by ASM-024 (10(-5) to 10(-)(3) M, p ASM-024 was reversed in the presence of muscarinic and nicotinic antagonists. In subjects with mild asthma, ASM-024 inhalation significantly inhibited basophil CD203c expression measured 24 h after allergen challenge (p = 0.03). This study shows that ASM-024 inhibits IgE- and allergen-induced basophil activation through both nicotinic and muscarinic receptors, and suggests that ASM-024 may be an efficacious agent for modulating allergic asthma responses. © 2015 S. Karger AG, Basel.

  5. Acid Sphingomyelinase (ASM) is a Negative Regulator of Regulatory T Cell (Treg) Development.

    Science.gov (United States)

    Zhou, Yuetao; Salker, Madhuri S; Walker, Britta; Münzer, Patrick; Borst, Oliver; Gawaz, Meinrad; Gulbins, Erich; Singh, Yogesh; Lang, Florian

    2016-01-01

    Regulatory T cell (Treg) is required for the maintenance of tolerance to various tissue antigens and to protect the host from autoimmune disorders. However, Treg may, indirectly, support cancer progression and bacterial infections. Therefore, a balance of Treg function is pivotal for adequate immune responses. Acid sphingomyelinase (ASM) is a rate limiting enzyme involved in the production of ceramide by breaking down sphingomyelin. Previous studies in T-cells have suggested that ASM is involved in CD28 signalling, T lymphocyte granule secretion, degranulation, and vesicle shedding similar to the formation of phosphatidylserine-exposing microparticles from glial cells. However, whether ASM affects the development of Treg has not yet been described. Splenocytes, isolated Naive T lymphocytes and cultured T cells were characterized for various immune T cell markers by flow cytometery. Cell proliferation was measured by Carboxyfluorescein succinimidyl ester (CFSE) dye, cell cycle analysis by Propidium Iodide (PI), mRNA transcripts by q-RT PCR and protein expression by Western Blotting respectively. ASM deficient mice have higher number of Treg compared with littermate control mice. In vitro induction of ASM deficient T cells in the presence of TGF-β and IL-2 lead to a significantly higher number of Foxp3+ induced Treg (iTreg) compared with control T-cells. Further, ASM deficient iTreg has less AKT (serine 473) phosphorylation and Rictor levels compared with control iTreg. Ceramide C6 led to significant reduction of iTreg in both ASM deficient and WT mice. The reduction in iTreg leads to induction of IL-1β, IL-6 and IL-17 but not IFN-γ mRNA levels. ASM is a negative regulator of natural and iTreg. © 2016 The Author(s) Published by S. Karger AG, Basel.

  6. ASM-024, a piperazinium compound, promotes the in vitro relaxation of β2-adrenoreceptor desensitized tracheas.

    Science.gov (United States)

    Israël-Assayag, Evelyne; Beaulieu, Marie-Josée; Cormier, Yvon

    2015-01-01

    Inhaled β2-adrenoreceptor agonists are widely used in asthma and chronic obstructive pulmonary disease (COPD) for bronchoconstriction relief. β2-Adrenoreceptor agonists relax airway smooth muscle cells via cyclic adenosine monophosphate (cAMP) mediated pathways. However, prolonged stimulation induces functional desensitization of the β2-adrenoreceptors (β2-AR), potentially leading to reduced clinical efficacy with chronic or prolonged administration. ASM-024, a small synthetic molecule in clinical stage development, has shown activity at the level of nicotinic receptors and possibly at the muscarinic level and presents anti-inflammatory and bronchodilator properties. Aerosolized ASM-024 reduces airway resistance in mice and promotes in-vitro relaxation of tracheal and bronchial preparations from animal and human tissues. ASM-024 increased in vitro relaxation response to maximally effective concentration of short-acting beta-2 agonists in dog and human bronchi. Although the precise mechanisms by which ASM-024 promotes airway smooth muscle (ASM) relaxation remain unclear, we hypothesized that ASM-024 will attenuate and/or abrogate agonist-induced contraction and remain effective despite β2-AR tachyphylaxis. β2-AR tachyphylaxis was induced with salbutamol, salmeterol and formoterol on guinea pig tracheas. The addition of ASM-024 relaxed concentration-dependently intact or β2-AR desensitized tracheal rings precontracted with methacholine. ASM-024 did not induce any elevation of intracellular cAMP in isolated smooth muscle cells; moreover, blockade of the cAMP pathway with an adenylate cyclase inhibitor had no significant effect on ASM-024-induced guinea pig trachea relaxation. Collectively, these findings show that ASM-024 elicits relaxation of β2-AR desensitized tracheal preparations and suggest that ASM-024 mediates smooth muscle relaxation through a different target and signaling pathway than β2-adrenergic receptor agonists. These findings suggest ASM-024

  7. Application of nuclear air cleaning and treatment codes

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1995-01-01

    All modifications to existing ventilation systems, as well as any new ventilation systems used on the Hanford Site are required to meet both American Society of Mechanical Engineers (ASME) codes N509 and N510. Difficulties encountered when applying code N509 at the Hanford Site include the composition of the ventilation air stream and requirements related to ventilation equipment procurement. Also, the existing ventilation systems for the waste tanks at the Hanford Site cannot be tested in accordance with code N510 because of the current configuration of these systems

  8. Application of nuclear air cleaning and treatment codes

    Energy Technology Data Exchange (ETDEWEB)

    Kriskovich, J.R. [Westinghouse Hanford Company, Richland, WA (United States)

    1995-02-01

    All modifications to existing ventilation systems, as well as any new ventilation systems used on the Hanford Site are required to meet both American Society of Mechanical Engineers (ASME) codes N509 and N510. Difficulties encountered when applying code N509 at the Hanford Site include the composition of the ventilation air stream and requirements related to ventilation equipment procurement. Also, the existing ventilation systems for the waste tanks at the Hanford Site cannot be tested in accordance with code N510 because of the current configuration of these systems.

  9. CERN's new arrivals, March 2004.

    CERN Document Server

    Patrice Loïez

    2004-01-01

    On Tuesday 9 March 2004, representatives of the CERN Management welcomed recently-recruited staff members and fellows at the trimester session of the Induction Programme (photographed here with Werner Zapf, Head of the Human Resources Department).

  10. Analytical considerations in the code qualification of piping systems

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1995-01-01

    The paper addresses several analytical topics in the design and qualification of piping systems which have a direct bearing on the prediction of stresses in the pipe and hence on the application of the equations of NB, NC and ND-3600 of the ASME Boiler and Pressure Vessel Code. For each of the analytical topics, the paper summarizes the current code requirements, if any, and the industry practice

  11. CERN Technical Training 2004: New Short Courses (SC) on Microsoft Outlook

    CERN Multimedia

    Monique Duval

    2004-01-01

    The CERN Technical Training programme is now proposing a new format for courses on Microsoft Outlook. Three two-hours Short Courses (SC) will cover basic and advanced functionalities of the recommended mail client for email at CERN. Each module can be followed independently. The next scheduled sessions will take place as follows: Outlook (SC I): E-mail. Next session: 31.8.2004 (9h00-11h00) Outlook (SC II): Calendar, Tasks and Notes. Next session: 31.8.2004 (14h00-16h00) Outlook (SC III): Meetings and Delegation. Next session: 7.9.2004 (14h00-16h00) In particular, SC I will cover how to open, create and send email, work with attachments, use stationery, organise mail, and work with the address book, SC II will show how to work with the calendar, tasks and notes, and SC III will cover how to organise and manage meetings, work with meeting requests, share tasks, and use email and calendar delegation. The number of participants to each session is limited to 8. The instructor is English-French bilingual, and she...

  12. NIST/ASME Steam Properties Database

    Science.gov (United States)

    SRD 10 NIST/ASME Steam Properties Database (PC database for purchase)   Based upon the International Association for the Properties of Water and Steam (IAPWS) 1995 formulation for the thermodynamic properties of water and the most recent IAPWS formulations for transport and other properties, this updated version provides water properties over a wide range of conditions according to the accepted international standards.

  13. High Level Analysis, Design and Validation of Distributed Mobile Systems with CoreASM

    Science.gov (United States)

    Farahbod, R.; Glässer, U.; Jackson, P. J.; Vajihollahi, M.

    System design is a creative activity calling for abstract models that facilitate reasoning about the key system attributes (desired requirements and resulting properties) so as to ensure these attributes are properly established prior to actually building a system. We explore here the practical side of using the abstract state machine (ASM) formalism in combination with the CoreASM open source tool environment for high-level design and experimental validation of complex distributed systems. Emphasizing the early phases of the design process, a guiding principle is to support freedom of experimentation by minimizing the need for encoding. CoreASM has been developed and tested building on a broad scope of applications, spanning computational criminology, maritime surveillance and situation analysis. We critically reexamine here the CoreASM project in light of three different application scenarios.

  14. A comparative study for SMART steam generator sizing based on ASME and Russian standard

    International Nuclear Information System (INIS)

    Kim, Y. W.; Kim, J. I.; Jang, M. H.

    2000-01-01

    A systematic comparison of ASME and Russian standard with respect to the design of SMART steam generator has been carried out. Classification of allowable stress in the Russian standard is quite different from that of ASME. Allowable stress of Russian standard and stress intensity defined in ASME were compared for various steam generator tube material as a function of design temperature. Equations and methodology of determining the thickness for the important parts of steam generator have been analyzed. For the tube subjected to internal and/or external pressure, Russian standard use the same equation in the sizing of tube with different allowable stress. However, ASME use different equations with the same value of allowable stress intensity. The hydraulic test pressure of ASME was also compared with that of Russian standard. In general, hydraulic test pressure determined by Russian standard is higher since it considers difference between allowable stress of test temperature and that of design temperature

  15. A minimal path searching approach for active shape model (ASM)-based segmentation of the lung

    Science.gov (United States)

    Guo, Shengwen; Fei, Baowei

    2009-02-01

    We are developing a minimal path searching method for active shape model (ASM)-based segmentation for detection of lung boundaries on digital radiographs. With the conventional ASM method, the position and shape parameters of the model points are iteratively refined and the target points are updated by the least Mahalanobis distance criterion. We propose an improved searching strategy that extends the searching points in a fan-shape region instead of along the normal direction. A minimal path (MP) deformable model is applied to drive the searching procedure. A statistical shape prior model is incorporated into the segmentation. In order to keep the smoothness of the shape, a smooth constraint is employed to the deformable model. To quantitatively assess the ASM-MP segmentation, we compare the automatic segmentation with manual segmentation for 72 lung digitized radiographs. The distance error between the ASM-MP and manual segmentation is 1.75 +/- 0.33 pixels, while the error is 1.99 +/- 0.45 pixels for the ASM. Our results demonstrate that our ASM-MP method can accurately segment the lung on digital radiographs.

  16. A Minimal Path Searching Approach for Active Shape Model (ASM)-based Segmentation of the Lung.

    Science.gov (United States)

    Guo, Shengwen; Fei, Baowei

    2009-03-27

    We are developing a minimal path searching method for active shape model (ASM)-based segmentation for detection of lung boundaries on digital radiographs. With the conventional ASM method, the position and shape parameters of the model points are iteratively refined and the target points are updated by the least Mahalanobis distance criterion. We propose an improved searching strategy that extends the searching points in a fan-shape region instead of along the normal direction. A minimal path (MP) deformable model is applied to drive the searching procedure. A statistical shape prior model is incorporated into the segmentation. In order to keep the smoothness of the shape, a smooth constraint is employed to the deformable model. To quantitatively assess the ASM-MP segmentation, we compare the automatic segmentation with manual segmentation for 72 lung digitized radiographs. The distance error between the ASM-MP and manual segmentation is 1.75 ± 0.33 pixels, while the error is 1.99 ± 0.45 pixels for the ASM. Our results demonstrate that our ASM-MP method can accurately segment the lung on digital radiographs.

  17. [Ca2+]i oscillations in ASM: relationship with persistent airflow obstruction in asthma.

    Science.gov (United States)

    Sweeney, David; Hollins, Fay; Gomez, Edith; Saunders, Ruth; Challiss, R A John; Brightling, Christopher E

    2014-07-01

    The cause of airway smooth muscle (ASM) hypercontractility in asthma is not fully understood. The relationship of spontaneous intracellular calcium oscillation frequency in ASM to asthma severity was investigated. Oscillations were increased in subjects with impaired lung function abolished by extracellular calcium removal, attenuated by caffeine and unaffected by verapamil or nitrendipine. Whether modulation of increased spontaneous intracellular calcium oscillations in ASM from patients with impaired lung function represents a therapeutic target warrants further investigation. © 2014 The Authors. Respirology published by Wiley Publishing Asia Pty Ltd on behalf of Asian Pacific Society of Respirology.

  18. A strategy for implementation of experience based seismic equipment qualification in IEEE and ASME industry standards

    International Nuclear Information System (INIS)

    Adams, T.M.

    1996-01-01

    In the past 20 years, extensive data on the performance of mechanical and electric equipment during actual strong motion earthquakes and seismic qualification tests has been accumulated. Recognizing that an experience based approach provides a technically sound and cost effective method for the seismic qualification of some or certain equipment, the IEEE Nuclear Power Engineering Committee and the ASME Committee on Qualification of Mechanical Equipment established a Special Working Group to investigate the incorporation of experienced based methods into the industry consensus codes and standards currently used in the seismic qualification of Seismic Category Nuclear Power Plant equipment. This paper presents the strategy (course of action) which was developed by the Special Working Group for meeting this objective of incorporation of experience based seismic qualification standards used in the design and seismic qualification of seismic category nuclear power plant equipment. This strategy was recommended to both chartering organizations, the IEEE Nuclear Power Engineering Committee and the ASME Committee on Qualification of Mechanical Equipment for their consideration and implementation. The status of the review and implementation of the Special Working Group's recommended strategy by the sponsoring organization is also discussed

  19. Code, standard and specifications

    International Nuclear Information System (INIS)

    Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

    2008-01-01

    Radiography also same as the other technique, it need standard. This standard was used widely and method of used it also regular. With that, radiography testing only practical based on regulations as mentioned and documented. These regulation or guideline documented in code, standard and specifications. In Malaysia, level one and basic radiographer can do radiography work based on instruction give by level two or three radiographer. This instruction was produced based on guideline that mention in document. Level two must follow the specifications mentioned in standard when write the instruction. From this scenario, it makes clearly that this radiography work is a type of work that everything must follow the rule. For the code, the radiography follow the code of American Society for Mechanical Engineer (ASME) and the only code that have in Malaysia for this time is rule that published by Atomic Energy Licensing Board (AELB) known as Practical code for radiation Protection in Industrial radiography. With the existence of this code, all the radiography must follow the rule or standard regulated automatically.

  20. ASM LabCap's contributions to disease surveillance and the International Health Regulations (2005).

    Science.gov (United States)

    Specter, Steven; Schuermann, Lily; Hakiruwizera, Celestin; Sow, Mah-Séré Keita

    2010-12-03

    The revised International Health Regulations [IHR(2005)], which requires the Member States of the World Health Organization (WHO) to develop core capacities to detect, assess, report, and respond to public health threats, is bringing new challenges for national and international surveillance systems. As more countries move toward implementation and/or strengthening of their infectious disease surveillance programs, the strengthening of clinical microbiology laboratories becomes increasingly important because they serve as the first line responders to detect new and emerging microbial threats, re-emerging infectious diseases, the spread of antibiotic resistance, and the possibility of bioterrorism. In fact, IHR(2005) Core Capacity #8, "Laboratory", requires that laboratory services be a part of every phase of alert and response.Public health laboratories in many resource-constrained countries require financial and technical assistance to build their capacity. In recognition of this, in 2006, the American Society for Microbiology (ASM) established an International Laboratory Capacity Building Program, LabCap, housed under the ASM International Board. ASM LabCap utilizes ASM's vast resources and its membership's expertise-40,000 microbiologists worldwide-to strengthen clinical and public health laboratory systems in low and low-middle income countries. ASM LabCap's program activities align with HR(2005) by building the capability of resource-constrained countries to develop quality-assured, laboratory-based information which is critical to disease surveillance and the rapid detection of disease outbreaks, whether they stem from natural, deliberate or accidental causes.ASM LabCap helps build laboratory capacity under a cooperative agreement with the U.S. Centers for Disease Control and Prevention (CDC) and under a sub-contract with the Program for Appropriate Technology in Health (PATH) funded by the United States Agency for International Development (USAID

  1. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  2. Manual phased arrays for weld inspections using North American codes

    International Nuclear Information System (INIS)

    Moles, Michael

    2008-01-01

    Phased arrays are primarily a method of generating and receiving ultrasound, not a new technology. In addition, the physics of ultrasound generated by phased arrays is identical to that from conventional monocrystals. Not surprisingly, all the major North American (and some European) codes accept phased arrays, either explicitly or implicitly. However, the technique and procedures needs to be proven, typically by a Performance Demonstration. The ASME (AmeicanSociety for Mechanical Engineers) Section V and API RP2X explicitly accept phased arrays. Three ASME code cases have been written specifically fo manual phased array: Code Cases 2541. 2557 and 2558. Over and above the general requirements of Article 4, these Code Cases require full waveform calibration. This is echoed in ASTM E-2491, a Standard Guide for setting up phased arrays. In addition. details such as focusing and reporting are addressed. The American Petroleum Institute QUTE procedure did not need any modifications to be compatible with manual phased arrays. The American Welding Society (AWS) Structural Welding Code D1.1 implicitly accepts phased arrays. New technologies such as phased arrays can be proven using Annex K. Nonetheless, a manual phased array unit using the standard AWS probe and displaying 45, 60 and 70degrees waveforms would be acceptable for D1.1 a s is . Overall, most major North American codes accept phased arrays, however, the technique and procedures must be proven, often using a Performance Demonstration. (author)

  3. 14 CFR 330.31 - What data must air carriers submit concerning ASMs or RTMs?

    Science.gov (United States)

    2010-01-01

    ... combination passenger/cargo carrier, you must have submitted your August 2001 total completed ASM report to... correct an error that you document to the Department, you must not alter the ASM or RTM reports you...

  4. Technical Challenge and Demonstration of Advanced Solution Monitoring and Measurement System (ASMS)

    International Nuclear Information System (INIS)

    Takaya, A.; Mukai, Y.; Nakamura, H.; Hosoma, T.; Yoshimoto, K.; Tamura, T.; Iwamoto, T.

    2010-01-01

    JNFL and JAEA have collaboratively started to develop an Advanced Solution Measurement and monitoring System (ASMS) as a part of technical challenge intended for next generation safeguards NDA equipment. After we completed feasibility study by using small detectors, the second stage of ASMS has installed into PCDF tank located in a cell, and then tested and calibrated by Pu nitrate solution experimentally. There was no experience measuring around 50kg Pu inventory directly, so it was very challenging work. The conventional SMMS (Solution Monitoring and Measurement System) that is composed of precision manometers acquires density, level and temperature of solution, so that the sampling and analysis are essential to obtain the nuclear material amount in the tank. The SMMS has two weak points on verification and monitoring of the nuclear material flow and inventory; (1) Direct measurement of the inventory cannot be done, (2) Solution rework and reagent adjustment operation in actual plant will make miss-interpretation on the monitoring evaluation. The purpose of ASMS development is to establish quantitative plutonium mass measurement technique directly by NDA of high concentrated pure plutonium nitrate solution and monitoring capability for solution transfers in a process. The merits of ASMS are considered below; (1) Provide direct Pu measurement and continuous monitoring capability, (2) Eliminate sampling and analysis at IIV, (3) Reduce unmeasured inventory. The target of the measurement uncertainty of ASMS is set less than 6% (1sigma) which is equivalent to meet the detection level of the partial defect at IIV by NDA. Known-alpha coincidence counting technique is applied to the ASMS, which is similar to the NDAs for MOX powder as a principle measurement technique. Especially, three following points are key techniques to establish ASMS. (1) Pre-determination of plutonium isotopic composition because it impacts alpha and rho-zero values to obtain multiplication

  5. The ASM Curriculum Guidelines for Undergraduate Microbiology: A Case Study of the Advocacy Role of Societies in Reform Efforts.

    Science.gov (United States)

    Horak, Rachel E A; Merkel, Susan; Chang, Amy

    2015-05-01

    A number of national reports, including Vision and Change in Undergraduate Biology Education: A Call to Action, have called for drastic changes in how undergraduate biology is taught. To that end, the American Society for Microbiology (ASM) has developed new Curriculum Guidelines for undergraduate microbiology that outline a comprehensive curriculum for any undergraduate introductory microbiology course or program of study. Designed to foster enduring understanding of core microbiology concepts, the Guidelines work synergistically with backwards course design to focus teaching on student-centered goals and priorities. In order to qualitatively assess how the ASM Curriculum Guidelines are used by educators and learn more about the needs of microbiology educators, the ASM Education Board distributed two surveys to the ASM education community. In this report, we discuss the results of these surveys (353 responses). We found that the ASM Curriculum Guidelines are being implemented in many different types of courses at all undergraduate levels. Educators indicated that the ASM Curriculum Guidelines were very helpful when planning courses and assessments. We discuss some specific ways in which the ASM Curriculum Guidelines have been used in undergraduate classrooms. The survey identified some barriers that microbiology educators faced when trying to adopt the ASM Curriculum Guidelines, including lack of time, lack of financial resources, and lack of supporting resources. Given the self-reported challenges to implementing the ASM Curriculum Guidelines in undergraduate classrooms, we identify here some activities related to the ASM Curriculum Guidelines that the ASM Education Board has initiated to assist educators in the implementation process.

  6. The ASM Curriculum Guidelines for Undergraduate Microbiology: A Case Study of the Advocacy Role of Societies in Reform Efforts

    Directory of Open Access Journals (Sweden)

    Rachel E.A. Horak

    2015-03-01

    Full Text Available A number of national reports, including Vision and Change in Undergraduate Biology Education: A Call to Action, have called for drastic changes in how undergraduate biology is taught. To that end, the American Society for Microbiology (ASM developed new Curriculum Guidelines for undergraduate microbiology that outline a comprehensive curriculum for any undergraduate introductory microbiology course or program of study. Designed to foster enduring understanding of core microbiology concepts, the Guidelines work synergistically with backwards course design to focus teaching on student-centered goals and priorities.  In order to qualitatively assess how the ASM Curriculum Guidelines are used by educators and learn more about the needs of microbiology educators, the ASM Education Board distributed two surveys to the ASM education community. In this report, we discuss results of these surveys (353 responses. We found that the ASM Curriculum Guidelines are being implemented in many different types of courses at all undergraduate levels. Educators indicated that the ASM Curriculum Guidelines were very helpful when planning courses and assessments. We discuss some specific ways in which the ASM Curriculum Guidelines have been used in undergraduate classrooms. The survey identified some barriers that microbiology educators faced when trying to adopt the ASM Curriculum Guidelines, including lack of time, lack of financial resources, and lack of supporting resources. Given the self-reported challenges to implementing the ASM Curriculum Guidelines in undergraduate classrooms, we identify here some activities related to the ASM Curriculum Guidelines that the ASM Education Board has initiated to assist educators in the implementation process.

  7. 115-year-old society knows how to reach young scientists: ASM Young Ambassador Program.

    Science.gov (United States)

    Karczewska-Golec, Joanna

    2015-12-25

    With around 40,000 members in more than 150 countries, American Society for Microbiology (ASM) faces the challenge of meeting very diverse needs of its increasingly international members base. The newly launched ASM Young Ambassador Program seeks to aid the Society in this effort. Equipped with ASM conceptual support and financing, Young Ambassadors (YAs) design and pursue country-tailored approaches to strengthen the Society's ties with local microbiological communities. In a trans-national setting, the active presence of YAs at important scientific events, such as 16th European Congress on Biotechnology, forges new interactions between ASM and sister societies. The paper presents an overview of the Young Ambassadors-driven initiatives at both global and country levels, and explores the topic of how early-career scientists can contribute to science diplomacy and international relations. Copyright © 2014 Elsevier B.V. All rights reserved.

  8. Technical Training: CERN Technical Training 2004 - New Short Courses (SC) on Microsoft Outlook

    CERN Multimedia

    Monique Duval

    2004-01-01

    The CERN Technical Training programme is now proposing a new format for courses on Microsoft Outlook. Three two-hours Short Courses (SC) will cover basic and advanced functionalities of the recommended mail client for email at CERN. Each module can be followed independently. The next scheduled sessions will take place as follows: Outlook (SC I): E-mail. Next session: 31.8.2004 (9h00-11h00) Outlook (SC II): Calendar, Tasks and Notes. Next session: 31.8.2004 (14h00-16h00) Outlook (SC III): Meetings and Delegation. Next session: 7.9.2004 (14h00-16h00) In particular, SC I will cover how to open, create and send email, work with attachments, use stationery, organise mail, and work with the address book, SC II will show how to work with the calendar, tasks and notes, and SC III will cover how to organise and manage meetings, work with meeting requests, share tasks, and use email and calendar delegation. The number of participants to each session is limited to 8. The instructor is English-French bilingual, and s...

  9. Structural and functional analysis of the ASM p.Ala359Asp mutant that causes acid sphingomyelinase deficiency.

    Science.gov (United States)

    Acuña, Mariana; Castro-Fernández, Víctor; Latorre, Mauricio; Castro, Juan; Schuchman, Edward H; Guixé, Victoria; González, Mauricio; Zanlungo, Silvana

    2016-10-21

    Niemann-Pick disease (NPD) type A and B are recessive hereditary disorders caused by deficiency in acid sphingomyelinase (ASM). The p.Ala359Asp mutation has been described in several patients but its functional and structural effects in the protein are unknown. In order to characterize this mutation, we modeled the three-dimensional ASM structure using the recent available crystal of the mammalian ASM as a template. We found that the p.Ala359Asp mutation is localized in the hydrophobic core and far from the sphingomyelin binding site. However, energy function calculations using statistical potentials indicate that the mutation causes a decrease in ASM stability. Therefore, we investigated the functional effect of the p.Ala359Asp mutation in ASM expression, secretion, localization and activity in human fibroblasts. We found a 3.8% residual ASM activity compared to the wild-type enzyme, without changes in the other parameters evaluated. These results support the hypothesis that the p.Ala359Asp mutation causes structural alterations in the hydrophobic environment where ASM is located, decreasing its enzymatic activity. A similar effect was observed in other previously described NPDB mutations located outside the active site of the enzyme. This work shows the first full size ASM mutant model describe at date, providing a complete analysis of the structural and functional effects of the p.Ala359Asp mutation over the stability and activity of the enzyme. Copyright © 2016 Elsevier Inc. All rights reserved.

  10. Roles of the outer membrane protein AsmA of Salmonella enterica in the control of marRAB expression and invasion of epithelial cells.

    Science.gov (United States)

    Prieto, Ana I; Hernández, Sara B; Cota, Ignacio; Pucciarelli, M Graciela; Orlov, Yuri; Ramos-Morales, Francisco; García-del Portillo, Francisco; Casadesús, Josep

    2009-06-01

    A genetic screen for suppressors of bile sensitivity in DNA adenine methylase (dam) mutants of Salmonella enterica serovar Typhimurium yielded insertions in an uncharacterized locus homologous to the Escherichia coli asmA gene. Disruption of asmA suppressed bile sensitivity also in phoP and wec mutants of S. enterica and increased the MIC of sodium deoxycholate for the parental strain ATCC 14028. Increased levels of marA mRNA were found in asmA, asmA dam, asmA phoP, and asmA wec strains of S. enterica, suggesting that lack of AsmA activates expression of the marRAB operon. Hence, asmA mutations may enhance bile resistance by inducing gene expression changes in the marRAB-controlled Mar regulon. In silico analysis of AsmA structure predicted the existence of one transmembrane domain. Biochemical analysis of subcellular fractions revealed that the asmA gene of S. enterica encodes a protein of approximately 70 kDa located in the outer membrane. Because AsmA is unrelated to known transport and/or efflux systems, we propose that activation of marRAB in asmA mutants may be a consequence of envelope reorganization. Competitive infection of BALB/c mice with asmA(+) and asmA isogenic strains indicated that lack of AsmA attenuates Salmonella virulence by the oral route but not by the intraperitoneal route. Furthermore, asmA mutants showed a reduced ability to invade epithelial cells in vitro.

  11. The approach to analysis of significance of flaws in ASME section III and section XI

    International Nuclear Information System (INIS)

    Cowan, A.

    1979-01-01

    ASME III Appendix G and ASME XI Appendix A describe linear elastic fracture mechanics methods to assess the significance of defects in thick-walled pressure vessels for nuclear reactor systems. The assessment of fracture toughness, Ksub(Ic), is based upon recommendations made by a Task Group of the USA Pressure Vessel Research Committee and is dependent upon correlations with drop weight and Charpy V-notch data to give a lower bound of fracture toughness Ksub(IR). The methods used in the ASME Appendices are outlined noting that, whereas ASME III Appendix G defines a procedure for obtaining allowable pressure vessel loadings for normal service in the presence of a defect, ASME XI Appendix A defines methods for assessing the significance of defects (found by volumetric inspection) under normal and emergency and faulted conditions. The methods of analysis are discussed with respect to material properties, flaw characterisation, stress analysis and recommended safety factors; a short discussion is given on the applicability of the data and methods to other materials and non-nuclear structures. (author)

  12. Neurospora crassa ASM-1 complements the conidiation defect in a stuA mutant of Aspergillus nidulans.

    Science.gov (United States)

    Chung, Dawoon; Upadhyay, Srijana; Bomer, Brigitte; Wilkinson, Heather H; Ebbole, Daniel J; Shaw, Brian D

    2015-01-01

    Aspergillus nidulans StuA and Neurospora crassa ASM-1 are orthologous APSES (ASM-1, PHD1, SOK2, Efg1, StuA) transcription factors conserved across a diverse group of fungi. StuA and ASM-1 have roles in asexual (conidiation) and sexual (ascospore formation) development in both organisms. To address the hypothesis that the last common ancestor of these diverse fungi regulated conidiation with similar genes, asm-1 was introduced into the stuA1 mutant of A. nidulans. Expression of asm-1 complemented defective conidiophore morphology and restored conidia production to wild type levels in stuA1. Expression of asm-1 in the stuA1 strain did not rescue the defect in sexual development. When the conidiation regulator AbaA was tagged at its C-terminus with GFP in A. nidulans, it localized to nuclei in phialides. When expressed in the stuA1 mutant, AbaA::GFP localized to nuclei in conidiophores but no longer was confined to phialides, suggesting that expression of AbaA in specific cell types of the conidiophore was conditioned by StuA. Our data suggest that the function in conidiation of StuA and ASM-1 is conserved and support the view that, despite the great morphological and ontogenic diversity of their condiphores, the last common ancestor of A. nidulans and N. crassa produced an ortholog of StuA that was involved in conidiophore development. © 2015 by The Mycological Society of America.

  13. Corticosteroids reduce IL-6 in ASM cells via up-regulation of MKP-1.

    Science.gov (United States)

    Quante, Timo; Ng, Yee Ching; Ramsay, Emma E; Henness, Sheridan; Allen, Jodi C; Parmentier, Johannes; Ge, Qi; Ammit, Alaina J

    2008-08-01

    The mechanisms by which corticosteroids reduce airway inflammation are not completely understood. Traditionally, corticosteroids were thought to inhibit cytokines exclusively at the transcriptional level. Our recent evidence, obtained in airway smooth muscle (ASM), no longer supports this view. We have found that corticosteroids do not act at the transcriptional level to reduce TNF-alpha-induced IL-6 gene expression. Rather, corticosteroids inhibit TNF-alpha-induced IL-6 secretion by reducing the stability of the IL-6 mRNA transcript. TNF-alpha-induced IL-6 mRNA decays at a significantly faster rate in ASM cells pretreated with the corticosteroid dexamethasone (t(1/2) = 2.4 h), compared to vehicle (t(1/2) = 9.0 h; P ASM cells.

  14. Flexural behavior of concrete beam with mechanical splices of reinforcement subjected to cyclic loading

    International Nuclear Information System (INIS)

    Nab, H. S.; Kim, W. B.

    2008-01-01

    In nuclear power plant structures, the mechanical rebar splices are designated and constructed on the basis of ACI and ASME code. Regardless of good performance on mechanical rebar splices, these splicing methods that did not be registered on ASME code have not restricted to apply to construction site. In this study, the main candidate splice is cold roll formed parallel threaded splice. This was registered newly in ASME Section III division 2 CC 4333 'Mechanical Splices' in 2004. To compare the traditional rebar splice with mechanical rebar splices, concrete beams were made to evaluate the ductility of spliced reinforcing bars. Based on Experimental results, it was identified that the mechanical rebar splices by parallel threaded coupler had better accumulated dissipation energy capacity to resist seismic behavior than the traditional lapping splices. It showed that concrete specimens with D36 reinforcing bar coupler are 1.8 times better performance and that concrete specimens with D22 reinforcing bar coupler are 2.8 times better performance. (authors)

  15. Fatigue-crack propagation behavior of steels in vacuum, and implications for ASME Section 11 crack growth analyses

    International Nuclear Information System (INIS)

    James, L.A.

    1985-08-01

    Section XI of the ASME Boiler and Pressure Vessel Code provides rules for the analysis of structures for which cracks or crack-like flaws have been discovered during inservice inspection. The Code provides rules for the analysis of both surface flaws as well as flaws that are embedded within the wall of the pressure vessel. In the case of surface flaws, the Code provides fatigue crack growth rate relationships for typical nuclear pressure vessel steels (e.g., ASTM A508-2 and A533-B) cycled in water environments typical of those in light-water reactors (LWR). However, for the case of embedded cracks, the Code provides crack growth relationships based on results from specimens that were cycled in an elevated temperature air environment. Although these latter relationships are often referred to as applying to ''inert'' environments, the results of this paper will show that an elevated temperature air environment is anything but inert, and that use of such relationships can result in overly pessimistic estimates of fatigue-crack growth lifetimes of embedded cracks. The reason, of course, is that embedded cracks grow in an environment that is probably much closer to a vacuum than an air environment

  16. Changing priorities of codes and standards -- quality engineering: Experiences in plant construction, maintenance, and operation

    International Nuclear Information System (INIS)

    Antony, D.D.; Suleski, P.F.; Meier, J.C.

    1994-01-01

    Application of the ASME Code across various fossil and nuclear plants necessitates a Company approach adapted by unique status of each plant. This arises from State Statutes, Federal Regulations and consideration of each plant's as-built history over a broad time frame of design, construction and operation. Additionally, the National Board Inspection Code accompanies Minnesota Statutes for plants owned by Northern States Power Company. This paper addresses some key points on NSP's use of ASME Code as a principal mechanical standard in plant design, construction and operation. A primary resource facilitating review of Code provisions is accurate status on current plant configuration. As plant design changes arise, the Code Edition/Addenda of original construction and installed upgrades or replacements are considered against available options allowed by current standards and dialog with the Jurisdictional Authority. Consistent with the overall goal of safe and reliable plant operation, there are numerous Code details and future needs to be addressed in concert with expected plant economics and planned outages for implementation. The discussion begins in the late 60's with new construction of Monticello and Prairie Island (both nuclear), through Sherburne County Units 1 through 3 (fossil), and their changes, replacements or repairs as operating plants

  17. Proceedings: 2001 ASME/EPRI Radwaste Workshop

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear utilities continually evaluate methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has increased the emphasis on this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technology and management improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

  18. Revision of the ASME nuclear quality assurance standard and its historical background

    International Nuclear Information System (INIS)

    Suzuki, Tetsuya

    2009-01-01

    ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

  19. A Video Recall Study of In-session Changes in Sentiment Override.

    Science.gov (United States)

    Johnson, Lee N; Tambling, Rachel B; Anderson, Shayne R

    2015-09-01

    This study examines in-session changes in sentiment override over the first three sessions of couple therapy. Couples viewed a video recording of therapy sessions immediately after each of the first three sessions and continuously rated their level of sentiment override. Ninety-eight changes were randomly chosen for analysis. Three talk turns prior to each change was coded using the Family Relational Communication Control Coding System. Results show that changes in sentiment override occur frequently. Repeated incidents of communication control were related to negative change in sentiment override for females. Repeated incidents of being left out of the conversation were related to negative changes in sentiment override for females and positive changes for males. © 2014 Family Process Institute.

  20. Cyclin D1 in ASM Cells from Asthmatics Is Insensitive to Corticosteroid Inhibition.

    Science.gov (United States)

    Allen, Jodi C; Seidel, Petra; Schlosser, Tobias; Ramsay, Emma E; Ge, Qi; Ammit, Alaina J

    2012-01-01

    Hyperplasia of airway smooth muscle (ASM) is a feature of the remodelled airway in asthmatics. We examined the antiproliferative effectiveness of the corticosteroid dexamethasone on expression of the key regulator of G(1) cell cycle progression-cyclin D1-in ASM cells from nonasthmatics and asthmatics stimulated with the mitogen platelet-derived growth factor BB. While cyclin D1 mRNA and protein expression were repressed in cells from nonasthmatics in contrast, cyclin D1 expression in asthmatics was resistant to inhibition by dexamethasone. This was independent of a repressive effect on glucocorticoid receptor translocation. Our results corroborate evidence demonstrating that corticosteroids inhibit mitogen-induced proliferation only in ASM cells from subjects without asthma and suggest that there are corticosteroid-insensitive proliferative pathways in asthmatics.

  1. 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)

  2. Proceedings: 2000 ASME/EPRI Radwaste Workshop

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear utilities are continually evaluating methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has added increased emphasis to this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technological and managerial improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

  3. Current and proposed revisions, changes, and modifications to American codes and standards to address packaging, handling, and transportation of radioactive materials and how they relate to comparable international regulations

    International Nuclear Information System (INIS)

    Borter, W.H.; Froehlich, C.H.

    2004-01-01

    This paper addresses current and proposed revisions, additions, and modifications to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) (i.e., ''ASMEthe Code'') Section III, Division 3 and American National Standards Institute (ANSI)/ASME N14.6. It provides insight into the ongoing processes of the associated committees and highlights important revisions, changes, and modifications to this Code and Standard. The ASME Code has developed and issued Division 3 to address items associated with the transportation and storage of radioactive materials. It currently only addresses ''General Requirements'' in Subsections WA and ''Class TP (Type B) Containments'' (Transportation Packages) in Subsection WB, but is in the process of adding a new Subsection WC to address ''Class SC'' (Storage Containments). ANSI/ASME Standard N14.6 which interacts with components constructed to Division 3 by addressinges special lifting devices for radioactive material shipping containers. This Standard is in the process of a complete re-write. This Code and Standard can be classified as ''dynamic'' in that their committees meet at least four times a year to evaluate proposed modifications and additions that reflect current safety practices in the nuclear industry. These evaluations include the possible addition of new materials, fabrication processes, examination methods, and testing requirements. An overview of this ongoing process is presented in this paper along with highlights of the more important proposed revisions, changes, and modifications and how they relate to United States (US) and international regulations and guidance like International Atomic Energy Agency (IAEA) Requirement No. TS-R-1

  4. Proceedings of the 2004 symposium on nuclear data

    International Nuclear Information System (INIS)

    Tahara, Yoshihisa; Fukahori, Tokio

    2005-03-01

    The 2004 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 11th and 12th of November 2004. Japanese Nuclear Data Committee and Nuclear Data Center, JAERI organized this symposium. In the oral sessions, presented were 19 papers on topics of nuclear data for LWR and nuclear fuel cycle, nuclear data for ADS development, experiences from use of JENDL-3.3 and requests to JENDL-4, recent cross section measurements, nuclear data for life and material sciences, and nuclear data needs and activities in the World. In the poster session, presented were 21 papers concerning experiments, evaluations, benchmark tests, applications and so on. Those presented papers are compiled in the proceedings. The 40 of the presented papers are indexed individually. (J.P.N.)

  5. Evaluation of the plastic characteristics of piping products in relation to ASME code criteria

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.; Moore, S.E.

    1978-07-01

    Theories and test data relevant to the plastic characteristics of piping products are presented and compared with Code Equations in NB-3652 for Class 1 piping; in NC/ND-3652.2 for Class 2 and Class 3 piping. Comparisons are made for (a) straight pipe, (b) elbows, (c) branch connections, and (d) tees. The status of data (or lack of data) for other piping components is discussed. Comparisons are made between available data and the Code equations for two typical piping materials, SA106 Grade B and SA312 TP304, for Code Design Limits, and Service Limits A, B, C, and D. Conditions under which the Code Limits cannot be shown to be conservative from available data are pointed out. Based on the results of the study, recommendations for Code revisions are presented, along with recommendations for additional work

  6. On-line monitoring and inservice inspection in codes

    International Nuclear Information System (INIS)

    Bartonicek, J.; Zaiss, W.; Bath, H.R.

    1999-01-01

    The relevant regulatory codes determine the ISI tasks and the time intervals for recurrent components testing for evaluation of operation-induced damaging or ageing in order to ensure component integrity on the basis of the last available quality data. In-service quality monitoring is carried out through on-line monitoring and recurrent testing. The requirements defined by the engineering codes elaborated by various institutions are comparable, with the KTA nuclear engineering and safety codes being the most complete provisions for quality evaluation and assurance after different, defined service periods. German conventional codes for assuring component integrity provide exclusively for recurrent inspection regimes (mainly pressure tests and optical testing). The requirements defined in the KTA codes however always demanded more specific inspections relying on recurrent testing as well as on-line monitoring. Foreign codes for ensuring component integrity concentrate on NDE tasks at regular time intervals, with time intervals scope of testing activities being defined on the basis of the ASME code, section XI. (orig./CB) [de

  7. Section XI ASME B and PV CODE, future trends, nondestructive examination requirements

    International Nuclear Information System (INIS)

    Cowfer, C.D.

    1984-01-01

    Service Induced Flaws such as intergranular stress corrosion cracking, Round Robin Programs like PISC II, and related developments in UT methodology and signal processing the past one to two years will have major impact on the Code and future NDE requirements. The performance of NDE has become a high exposure item which demands high reliability and accuracy; terms generally not used with field NDE in the past. The trend is out of ''cookbook'' requirements and into performance demonstration for personnel, procedures and equipment. This paper highlights the current major transition in the Code regarding NDE performance from the viewpoint of the author's involvement

  8. Interaction between endoplasmic/sarcoplasmic reticulum stress (ER/SR stress), mitochondrial signaling and Ca(2+) regulation in airway smooth muscle (ASM).

    Science.gov (United States)

    Delmotte, Philippe; Sieck, Gary C

    2015-02-01

    Airway inflammation is a key aspect of diseases such as asthma. Several inflammatory cytokines (e.g., TNFα and IL-13) increase cytosolic Ca(2+) ([Ca(2+)]cyt) responses to agonist stimulation and Ca(2+) sensitivity of force generation, thereby enhancing airway smooth muscle (ASM) contractility (hyper-reactive state). Inflammation also induces ASM proliferation and remodeling (synthetic state). In normal ASM, the transient elevation of [Ca(2+)]cyt induced by agonists leads to a transient increase in mitochondrial Ca(2+) ([Ca(2+)]mito) that may be important in matching ATP production with ATP consumption. In human ASM (hASM) exposed to TNFα and IL-13, the transient increase in [Ca(2+)]mito is blunted despite enhanced [Ca(2+)]cyt responses. We also found that TNFα and IL-13 induce reactive oxidant species (ROS) formation and endoplasmic/sarcoplasmic reticulum (ER/SR) stress (unfolded protein response) in hASM. ER/SR stress in hASM is associated with disruption of mitochondrial coupling with the ER/SR membrane, which relates to reduced mitofusin 2 (Mfn2) expression. Thus, in hASM it appears that TNFα and IL-13 result in ROS formation leading to ER/SR stress, reduced Mfn2 expression, disruption of mitochondrion-ER/SR coupling, decreased mitochondrial Ca(2+) buffering, mitochondrial fragmentation, and increased cell proliferation.

  9. Roles of the Outer Membrane Protein AsmA of Salmonella enterica in the Control of marRAB Expression and Invasion of Epithelial Cells▿

    OpenAIRE

    Prieto, Ana I.; Hernández, Sara B.; Cota, Ignacio; Pucciarelli, M. Graciela; Orlov, Yuri; Ramos-Morales, Francisco; García-del Portillo, Francisco; Casadesús, Josep

    2009-01-01

    A genetic screen for suppressors of bile sensitivity in DNA adenine methylase (dam) mutants of Salmonella enterica serovar Typhimurium yielded insertions in an uncharacterized locus homologous to the Escherichia coli asmA gene. Disruption of asmA suppressed bile sensitivity also in phoP and wec mutants of S. enterica and increased the MIC of sodium deoxycholate for the parental strain ATCC 14028. Increased levels of marA mRNA were found in asmA, asmA dam, asmA phoP, and asmA wec strains of S....

  10. Relaxation of inservice test frequency requirement for Kori 1 ASME code pumps

    International Nuclear Information System (INIS)

    Sohn, Gap Heon; Choi, Hae Yoon; Min, Kyung Sung; Rim, Nam Jin

    1994-08-01

    The objective of this investigation is to evaluate the technical and regulational requirements to justify the relaxation of the test frequency of Kori 1 pumps through reviewing the related rules and codes and standards, technical specifications of Kori 1 and other similar plants, standard technical specifications, research results for tech. spec. improvements and site test records. It is concluded that the relaxation of test frequency to quarterly be justified based on the conformance with rules and codes and standard, quarterly test cases in similar plants and standard tech. spec., recommendations of research result and stable site test records. (Author) 16 refs., 26 figs., 13 tabs

  11. Content Coding of Psychotherapy Transcripts Using Labeled Topic Models.

    Science.gov (United States)

    Gaut, Garren; Steyvers, Mark; Imel, Zac E; Atkins, David C; Smyth, Padhraic

    2017-03-01

    Psychotherapy represents a broad class of medical interventions received by millions of patients each year. Unlike most medical treatments, its primary mechanisms are linguistic; i.e., the treatment relies directly on a conversation between a patient and provider. However, the evaluation of patient-provider conversation suffers from critical shortcomings, including intensive labor requirements, coder error, nonstandardized coding systems, and inability to scale up to larger data sets. To overcome these shortcomings, psychotherapy analysis needs a reliable and scalable method for summarizing the content of treatment encounters. We used a publicly available psychotherapy corpus from Alexander Street press comprising a large collection of transcripts of patient-provider conversations to compare coding performance for two machine learning methods. We used the labeled latent Dirichlet allocation (L-LDA) model to learn associations between text and codes, to predict codes in psychotherapy sessions, and to localize specific passages of within-session text representative of a session code. We compared the L-LDA model to a baseline lasso regression model using predictive accuracy and model generalizability (measured by calculating the area under the curve (AUC) from the receiver operating characteristic curve). The L-LDA model outperforms the lasso logistic regression model at predicting session-level codes with average AUC scores of 0.79, and 0.70, respectively. For fine-grained level coding, L-LDA and logistic regression are able to identify specific talk-turns representative of symptom codes. However, model performance for talk-turn identification is not yet as reliable as human coders. We conclude that the L-LDA model has the potential to be an objective, scalable method for accurate automated coding of psychotherapy sessions that perform better than comparable discriminative methods at session-level coding and can also predict fine-grained codes.

  12. PIPE STRESS and VERPIP codes for stress analysis and verifications of PEC reactor piping

    International Nuclear Information System (INIS)

    Cesari, F.; Ferranti, P.; Gasparrini, M.; Labanti, L.

    1975-01-01

    To design LMFBR piping systems following ASME Sct. III requirements unusual flexibility computer codes are to be adopted to consider piping and its guard-tube. For this purpose PIPE STRESS code previously prepared by Southern-Service, has been modified. Some subroutine for detailed stress analysis and principal stress calculations on all the sections of piping have been written and fitted in the code. Plotter can also be used. VERPIP code for automatic verifications of piping as class 1 Sct. III prescriptions has been also prepared. The results of PIPE STRESS and VERPIP codes application to PEC piping are in section III of this report

  13. Simulation and optimization of a coking wastewater biological treatment process by activated sludge models (ASM).

    Science.gov (United States)

    Wu, Xiaohui; Yang, Yang; Wu, Gaoming; Mao, Juan; Zhou, Tao

    2016-01-01

    Applications of activated sludge models (ASM) in simulating industrial biological wastewater treatment plants (WWTPs) are still difficult due to refractory and complex components in influents as well as diversity in activated sludges. In this study, an ASM3 modeling study was conducted to simulate and optimize a practical coking wastewater treatment plant (CWTP). First, respirometric characterizations of the coking wastewater and CWTP biomasses were conducted to determine the specific kinetic and stoichiometric model parameters for the consecutive aeration-anoxic-aeration (O-A/O) biological process. All ASM3 parameters have been further estimated and calibrated, through cross validation by the model dynamic simulation procedure. Consequently, an ASM3 model was successfully established to accurately simulate the CWTP performances in removing COD and NH4-N. An optimized CWTP operation condition could be proposed reducing the operation cost from 6.2 to 5.5 €/m(3) wastewater. This study is expected to provide a useful reference for mathematic simulations of practical industrial WWTPs. Copyright © 2015 Elsevier Ltd. All rights reserved.

  14. Towards deductive verification of MPI programs against session types

    Directory of Open Access Journals (Sweden)

    Eduardo R. B. Marques

    2013-12-01

    Full Text Available The Message Passing Interface (MPI is the de facto standard message-passing infrastructure for developing parallel applications. Two decades after the first version of the library specification, MPI-based applications are nowadays routinely deployed on super and cluster computers. These applications, written in C or Fortran, exhibit intricate message passing behaviours, making it hard to statically verify important properties such as the absence of deadlocks. Our work builds on session types, a theory for describing protocols that provides for correct-by-construction guarantees in this regard. We annotate MPI primitives and C code with session type contracts, written in the language of a software verifier for C. Annotated code is then checked for correctness with the software verifier. We present preliminary results and discuss the challenges that lie ahead for verifying realistic MPI program compliance against session types.

  15. Función adrenal y metabolismo lipídico en niños asmáticos tratados con budesonida

    Directory of Open Access Journals (Sweden)

    Paoli-de Valeri Mariela

    1999-01-01

    Full Text Available Objetivo. Evaluar el efecto de bajas dosis de budesonida inhalado sobre la función adrenal y el metabolismo lipídico en niños asmáticos. Material y métodos. Se estudiaron: 10 niños asmáticos (edad promedio, 8.6 años tratados con budesonida inhalado (200-300 µg/día por un lapso mayor a tres meses (grupo A; 15 niños asmáticos (edad promedio, 7.8 años sin tratamiento esteroideo (grupo B, y 10 niños no asmáticos (grupo C. Se determinaron los niveles de cortisol basal y postestímulo con ACTH, andrógenos adrenales, lípidos y cortisol urinario. Resultados. Entre los grupos A y B no hubo diferencias significativas en las variables estudiadas. En los niños asmáticos (grupo A-B el cortisol urinario fue significativamente mayor en relación con el grupo C. Los niveles de triglicéridos, colesterol total, colesterol de la lipoproteína de baja densidad e índices aterogénicos fueron mayores en el grupo de niños asmáticos, con y sin budesonida, comparados con el grupo C. Conclusiones. El tratamiento con dosis bajas de budesonida inhalado en niños asmáticos no modificó la función del eje adrenal ni el metabolismo lipídico. Los pacientes asmáticos presentaron un perfil lipídico aterogénico que podría incrementar el riesgo de enfermedad cardiovascular.

  16. Bibliometric Analyses Reveal Patterns of Collaboration between ASMS Members

    Science.gov (United States)

    Palmblad, Magnus; van Eck, Nees Jan

    2018-03-01

    We have explored the collaborative network of the current American Society for Mass Spectrometry (ASMS) membership using bibliometric methods. The analysis shows that 4249 members are connected in a single, large, co-authorship graph, including the majority of the most published authors in the field of mass spectrometry. The map reveals topographical differences between university groups and national laboratories, and that the co-authors with the strongest links have long worked together at the same location. We have collected and summarized information on the geographical distribution of members, showing a high coverage of active researchers in North America and Western Europe. Looking at research fields, we could also identify a number of new or `hot' topics among ASMS members. Interactive versions of the maps are available on-line at https://goo.gl/UBNFMQ (collaborative network) and https://goo.gl/WV25vm (research topics). [Figure not available: see fulltext.

  17. Review and comparison of WWER and LWR Codes and Standards

    International Nuclear Information System (INIS)

    Buckthorpe, D.; Tashkinov, A.; Brynda, J.; Davies, L.M.; Cueto-Felgeueroso, C.; Detroux, P.; Bieniussa, K.; Guinovart, J.

    2003-01-01

    The results of work on a collaborative project on comparison of Codes and Standards used for safety related components of the WWER and LWR type reactors is presented. This work was performed on behalf of the European Commission, Working Group Codes and Standards and considers areas such as rules, criteria and provisions, failure mechanisms , derivation and understanding behind the fatigue curves, piping, materials and aging, manufacturing and ISI. WWERs are essentially designed and constructed using the Russian PNAE Code together with special provisions in a few countries (e.g. Czech Republic) from national standards. The LWR Codes have a strong dependence on the ASME Code. Also within Western Europe other codes are used including RCC-M, KTA and British Standards. A comparison of procedures used in all these codes and standards have been made to investigate the potential for equivalencies between the codes and any grounds for future cooperation between eastern and western experts in this field. (author)

  18. A Retrospective Look at 20 Years of ASM Education Programs (1990-2010 and a Prospective Look at the Next 20 Years (2011-2030

    Directory of Open Access Journals (Sweden)

    Amy Chang

    2011-03-01

    Full Text Available The Education Board of the American Society for Microbiology (ASM was established in the mid-1970s to address the graduate and medical education needs of ASM members. Since then, I have watched our offerings evolve from a small, graduate-level travel grant program for ASM meetings to a growing suite of professional development and networking opportunities including fellowships, publications, and conferences. Along the way, our audience has expanded from  graduate students to undergraduate biology and K-12 teachers, students of all ages, researchers, and the public.I have been fortunate enough to watch several pivotal programs and projects support our growth and change the status quo by providing opportunities for biology educators to flourish. These include the: (i Coalition for Education in the Life Sciences, (ii ASM Division on Microbiology Education, (iii ASM Conference for Undergraduate Educators, (iv ASM Journal of Microbiology & Biology Education, and (v ASM Fellowship Fund. In this review, the background and details I offer on each initiative help explain ASM Education offerings, how our growth has been supported, and where are we headed.

  19. Bronchodilatory and anti-inflammatory effects of ASM-024, a nicotinic receptor ligand, developed for the treatment of asthma.

    Science.gov (United States)

    Assayag, Evelyne Israël; Beaulieu, Marie-Josée; Cormier, Yvon

    2014-01-01

    Conventional asthma and COPD treatments include the use of bronchodilators, mainly β2-adrenergic agonists, muscarinic receptor antagonists and corticosteroids or leukotriene antagonists as anti-inflammatory agents. These active drugs are administered either separately or given as a fixed-dose combination medication into a single inhaler. ASM-024, a homopiperazinium compound, derived from the structural modification of diphenylmethylpiperazinium (DMPP), has been developed to offer an alternative mechanism of action that could provide symptomatic control through combined anti-inflammatory and bronchodilator properties in a single entity. A dose-dependent inhibition of cellular inflammation in bronchoalveolar lavage fluid was observed in ovalbumin-sensitized mice, subsequently treated for 3 days by nose-only exposure with aerosolized ASM-024 at doses up to 3.8 mg/kg (ED50 = 0.03 mg/kg). The methacholine ED250 values indicated that airway hyperresponsivenness (AHR) to methacholine decreased following ASM-024 administration by inhalation at a dose of 1.5 mg/kg, with a value of 0.145 ± 0.032 mg/kg for ASM 024-treated group as compared to 0.088 ± 0.023 mg/kg for untreated mice. In in vitro isometric studies, ASM-024 elicited dose-dependent relaxation of isolated mouse tracheal, human, and dog bronchial preparations contracted with methacholine and guinea pig tracheas contracted with histamine. ASM-024 showed also a dose and time dependant protective effect on methacholine-induced contraction. Overall, with its combined anti-inflammatory, bronchodilating and bronchoprotective properties, ASM-024 may represent a new class of drugs with a novel pharmacological approach that could prove useful for the chronic maintenance treatment of asthma and, possibly, COPD.

  20. Codification of LMFBR rules and comparison of codes

    International Nuclear Information System (INIS)

    Faure, O.; Debaene, J.P.

    1993-01-01

    The first part of this report presents the basic RCC-MR (regles de conception et de construction des materiels mecaniques des ilots nucleaires, reacteurs a neutrons rapides) design rules and their purpose. The second part is a qualitative comparison between RCC-MR, Code case N47 (ASME) and ETSDG Guide (MONJU Guide), made on the following topics: negligible creep test, ratcheting, creep fatigue, buckling, piping rules. An outline is given on improvements to RCC-MR rules now in progress

  1. ASME codification of ductile cast iron cask for transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Saegusa, Toshiari; Arai, Taku

    2012-01-01

    The CRIEPI has been executing research and development on ductile cast iron cask for transport and storage of spent nuclear fuel in order to diversify options of the casks. Based on the research results, the CRIEPI proposed materials standards (Section II) and structural design standards (Section III) for the ductile cast iron cask to the authoritative and international ASME (American Society of Mechanical Engineers) Codes. For the Section II, the CRIEPI proposed the JIS G 5504 material with additional requirement prohibiting repair of cast body by welding, etc. as well as the ASTM A874 material to the Part A. In addition, the CRIEPI proposed design stress allowables, physical properties (thermal conductivity, modulus of elasticity, etc.), and external pressure chart to the Part D. For the Section III, the CRIEPI proposed a fracture toughness requirement of the ductile cast iron cask at -40degC to WB and WC of Division 3. Additionally, the CRIEPI proposed a design fatigue curve of the ductile cast iron cask to Appendix of Division 1. This report describes the outline of the proposed standards, their bases, and the deliberation process in order to promote proper usage of the code, future improvement, etc. (author)

  2. 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)

  3. ASM-3 acid sphingomyelinase functions as a positive regulator of the DAF-2/AGE-1 signaling pathway and serves as a novel anti-aging target.

    Directory of Open Access Journals (Sweden)

    Yongsoon Kim

    Full Text Available In C. elegans, the highly conserved DAF-2/insulin/insulin-like growth factor 1 receptor signaling (IIS pathway regulates longevity, metabolism, reproduction and development. In mammals, acid sphingomyelinase (ASM is an enzyme that hydrolyzes sphingomyelin to produce ceramide. ASM has been implicated in CD95 death receptor signaling under certain stress conditions. However, the involvement of ASM in growth factor receptor signaling under physiological conditions is not known. Here, we report that in vivo ASM functions as a positive regulator of the DAF-2/IIS pathway in C. elegans. We have shown that inactivation of asm-3 extends animal lifespan and promotes dauer arrest, an alternative developmental process. A significant cooperative effect on lifespan is observed between asm-3 deficiency and loss-of-function alleles of the age-1/PI 3-kinase, with the asm-3; age-1 double mutant animals having a mean lifespan 259% greater than that of the wild-type animals. The lifespan extension phenotypes caused by the loss of asm-3 are dependent on the functions of daf-16/FOXO and daf-18/PTEN. We have demonstrated that inactivation of asm-3 causes nuclear translocation of DAF-16::GFP protein, up-regulates endogenous DAF-16 protein levels and activates the downstream targeting genes of DAF-16. Together, our findings reveal a novel role of asm-3 in regulation of lifespan and diapause by modulating IIS pathway. Importantly, we have found that two drugs known to inhibit mammalian ASM activities, desipramine and clomipramine, markedly extend the lifespan of wild-type animals, in a manner similar to that achieved by genetic inactivation of the asm genes. Our studies illustrate a novel strategy of anti-aging by targeting ASM, which may potentially be extended to mammals.

  4. ASM-3 acid sphingomyelinase functions as a positive regulator of the DAF-2/AGE-1 signaling pathway and serves as a novel anti-aging target.

    Science.gov (United States)

    Kim, Yongsoon; Sun, Hong

    2012-01-01

    In C. elegans, the highly conserved DAF-2/insulin/insulin-like growth factor 1 receptor signaling (IIS) pathway regulates longevity, metabolism, reproduction and development. In mammals, acid sphingomyelinase (ASM) is an enzyme that hydrolyzes sphingomyelin to produce ceramide. ASM has been implicated in CD95 death receptor signaling under certain stress conditions. However, the involvement of ASM in growth factor receptor signaling under physiological conditions is not known. Here, we report that in vivo ASM functions as a positive regulator of the DAF-2/IIS pathway in C. elegans. We have shown that inactivation of asm-3 extends animal lifespan and promotes dauer arrest, an alternative developmental process. A significant cooperative effect on lifespan is observed between asm-3 deficiency and loss-of-function alleles of the age-1/PI 3-kinase, with the asm-3; age-1 double mutant animals having a mean lifespan 259% greater than that of the wild-type animals. The lifespan extension phenotypes caused by the loss of asm-3 are dependent on the functions of daf-16/FOXO and daf-18/PTEN. We have demonstrated that inactivation of asm-3 causes nuclear translocation of DAF-16::GFP protein, up-regulates endogenous DAF-16 protein levels and activates the downstream targeting genes of DAF-16. Together, our findings reveal a novel role of asm-3 in regulation of lifespan and diapause by modulating IIS pathway. Importantly, we have found that two drugs known to inhibit mammalian ASM activities, desipramine and clomipramine, markedly extend the lifespan of wild-type animals, in a manner similar to that achieved by genetic inactivation of the asm genes. Our studies illustrate a novel strategy of anti-aging by targeting ASM, which may potentially be extended to mammals.

  5. ASM-3 Acid Sphingomyelinase Functions as a Positive Regulator of the DAF-2/AGE-1 Signaling Pathway and Serves as a Novel Anti-Aging Target

    Science.gov (United States)

    Kim, Yongsoon; Sun, Hong

    2012-01-01

    In C. elegans, the highly conserved DAF-2/insulin/insulin-like growth factor 1 receptor signaling (IIS) pathway regulates longevity, metabolism, reproduction and development. In mammals, acid sphingomyelinase (ASM) is an enzyme that hydrolyzes sphingomyelin to produce ceramide. ASM has been implicated in CD95 death receptor signaling under certain stress conditions. However, the involvement of ASM in growth factor receptor signaling under physiological conditions is not known. Here, we report that in vivo ASM functions as a positive regulator of the DAF-2/IIS pathway in C. elegans. We have shown that inactivation of asm-3 extends animal lifespan and promotes dauer arrest, an alternative developmental process. A significant cooperative effect on lifespan is observed between asm-3 deficiency and loss-of-function alleles of the age-1/PI 3-kinase, with the asm-3; age-1 double mutant animals having a mean lifespan 259% greater than that of the wild-type animals. The lifespan extension phenotypes caused by the loss of asm-3 are dependent on the functions of daf-16/FOXO and daf-18/PTEN. We have demonstrated that inactivation of asm-3 causes nuclear translocation of DAF-16::GFP protein, up-regulates endogenous DAF-16 protein levels and activates the downstream targeting genes of DAF-16. Together, our findings reveal a novel role of asm-3 in regulation of lifespan and diapause by modulating IIS pathway. Importantly, we have found that two drugs known to inhibit mammalian ASM activities, desipramine and clomipramine, markedly extend the lifespan of wild-type animals, in a manner similar to that achieved by genetic inactivation of the asm genes. Our studies illustrate a novel strategy of anti-aging by targeting ASM, which may potentially be extended to mammals. PMID:23049887

  6. Abelian Sandpile Model (ASM) and Infinite Volume Limit

    Indian Academy of Sciences (India)

    ASM- Properties. Any possible sequence of topplings leads to the same stable configuration [Dhar]. The result of particle addition at and subsequent relaxation is given by an operator. £ бвд £ евд £. , where вд £. ¢. ¦. ¤ззз ¤ вг иг . £. ©. ¢ йа£. (Abelian). 7-b ...

  7. Code qualification of structural materials for AFCI advanced recycling reactors.

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L. (Nuclear Engineering Division); (ORNL)

    2012-05-31

    This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP

  8. Adjoint sensitivity analysis of the RELAPS/MOD3.2 two-fluid thermal-hydraulic code system

    International Nuclear Information System (INIS)

    Ionescu-Bujor, M.

    2000-10-01

    This work presents the implementation of the Adjoint Sensitivity Analysis Procedure (ASAP) for the non-equilibrium, non-homogeneous two-fluid model, including boron concentration and non-condensable gases, of the RELAP5/MOD3.2 code. The end-product of this implementation is the Adjoint Sensitivity Model (ASM-REL/TF), which is derived for both the differential and discretized equations underlying the two-fluid model with non-condensable(s). The consistency requirements between these two representations are also highlighted. The validation of the ASM-REL/TF has been carried out by using sample problems involving: (i) liquid-phase only, (ii) gas-phase only, and (iii) two-phase mixture (of water and steam). Thus the 'Two-Loops with Pumps' sample problem supplied with RELAP5/MOD3.2 has been used to verify the accuracy and stability of the numerical solution of the ASM-REL/TF when only the liquid-phase is present. Furthermore, the 'Edwards Pipe' sample problem, also supplied with RELAP5/MOD3.2, has been used to verify the accuracy and stability of the numerical solution of the ASM-REL/TF when both (i.e., liquid and gas) phases are present. In addition, the accuracy and stability of the numerical solution of the ASM-REL/TF have been verified when only the gas-phase is present by using modified 'Two-Loops with Pumps' and the 'Edwards Pipe' sample problems in which the liquid and two-phase fluids, respectively, were replaced by pure steam. The results obtained for these sample problems depict typical sensitivities of junction velocities and volume-averaged pressures to perturbations in initial conditions, and indicate that the numerical solution of the ASM-REL/TF is as robust, stable, and accurate as the original RELAP5/MOD3.2 calculations. In addition, the solution of the ASM-REL/TF has been used to calculate sample sensitivities of volume-averaged pressures to variations in the pump head. (orig.) [de

  9. Energy and Data Throughput for Asymmetric Inter-Session Network Coding

    DEFF Research Database (Denmark)

    Paramanathan, Achuthan; Heide, Janus; Pahlevani, Peyman

    2012-01-01

    on commercial platforms. The outcome of this paper confirms the analytical expression, and the results shows that even with a large asymmetric data rate there is a gain in terms of energy consumption and throughput when network coding is applied in compare to the case when network coding is not applied.......In this paper we investigate the impact of asymmetric traffic patterns on the energy consumption and throughput in a wireless multi hop network. Network coding is a novel technique for communication systems and a viable solution for wireless multi hop networks. State-of-the-art research is mainly...

  10. Proceedings of the 2004 NASA/ONR Circulation Control Workshop, Part 1

    Science.gov (United States)

    Jones, Gregory S. (Editor); Joslin, Ronald D. (Editor)

    2005-01-01

    As technological advances influence the efficiency and effectiveness of aerodynamic and hydrodynamic applications, designs and operations, this workshop was intended to address the technologies, systems, challenges and successes specific to Coanda driven circulation control in aerodynamics and hydrodynamics. A major goal of this workshop was to determine the 2004 state-of-the-art in circulation control and understand the roadblocks to its application. The workshop addressed applications, CFD, and experiments related to circulation control, emphasizing fundamental physics, systems analysis, and applied research. The workshop consisted of 34 single session oral presentations and written papers that focused on Naval hydrodynamic vehicles (e.g. submarines), Fixed Wing Aviation, V/STOL platforms, propulsion systems (including wind turbine systems), ground vehicles (automotive and trucks) and miscellaneous applications (e.g., poultry exhaust systems and vacuum systems). Several advanced CFD codes were benchmarked using a two-dimensional NCCR circulation control airfoil. The CFD efforts highlighted inconsistencies in turbulence modeling, separation and performance predictions.

  11. Tunable Sparse Network Coding for Multicast Networks

    DEFF Research Database (Denmark)

    Feizi, Soheil; Roetter, Daniel Enrique Lucani; Sørensen, Chres Wiant

    2014-01-01

    This paper shows the potential and key enabling mechanisms for tunable sparse network coding, a scheme in which the density of network coded packets varies during a transmission session. At the beginning of a transmission session, sparsely coded packets are transmitted, which benefits decoding...... complexity. At the end of a transmission, when receivers have accumulated degrees of freedom, coding density is increased. We propose a family of tunable sparse network codes (TSNCs) for multicast erasure networks with a controllable trade-off between completion time performance to decoding complexity...... a mechanism to perform efficient Gaussian elimination over sparse matrices going beyond belief propagation but maintaining low decoding complexity. Supporting simulation results are provided showing the trade-off between decoding complexity and completion time....

  12. Utilização de Ecolife® e Acibenzolar-s-metil (ASM no controle da antracnose da banana em pós-colheita Use of Ecolife® and Acibenzolar-S-metil (ASM on the control of antracnosis in banana post-harvest

    Directory of Open Access Journals (Sweden)

    Luciano Marinho Furtado

    2010-09-01

    Full Text Available O objetivo deste trabalho foi avaliar a ação dos produtos ASM e Ecolife no controle da antracnose pós-colheita em frutos de banana. Frutos sadios de banana, variedades maçã, prata, pacovan e cacau , em fase intermediária de maturação, foram imersos previamente em soluções de ASM e Ecolife e inoculados com Colletotrichum musae. Utilizou-se o delineamento inteiramente casualizado, em esquema fatorial com quatro repetições. Os resultados apresentados demonstraram a eficácia dos produtos nas concentrações de 5 ml/ L (Ecolife e 0,50g/ L (ASM no controle da antracnose nas variedades analisa das. A variedade cacau apresentou menor lesão quando tratada com o Ecolife (5,79 mm. Com relação ao efeito do ASM, a bana na prata demonstrou um melhor resultado, com tamanho médio de lesão de 5,62 mm. Com o decorrer do processo de maturação dos frutos houve um decréscimo na severidade da doença nas quatro variedades estudadas, exceto no tratamento testemunha, que continuou apresentando aumento no tamanho das lesões nos frutos e atingir a polpa ao final da maturação.The aim of this work was to evaluate the effects of ASM and Ecolife on the control of post-harvest antracnosis in banana. Banana fruits of Maçã, Prata, Pacovan and Figo varieties, at intermediate stage of maturation, were immersed in solutions of ASM and Ecolife and inoculated with Colletotrichum musae A completely randomized design was used, at a factorial scheme 4x2 (four varieties x two products with four replicates. The presented results demonstrated the susceptibility of the fruits to the disease, mainly Maça variety with lesion of 17,99 mm. It was demosntrated the effectiveness of products at concentrations of 5ml. L-1 (Ecolife and 0.50g. L-1 (ASM on antracnosis control. The Figo variety presented the smallest injuries when treated with Ecolife (5.79 mm. Regarding ASM effects, Prata variety demonstrated the best performance, with 5.62 mm of injuries diameter

  13. Current Status of the Elevated Temperature Structure Design Codes for VHTR

    International Nuclear Information System (INIS)

    Kim, Jong-Bum; Kim, Seok-Hoon; Park, Keun-Bae; Lee, Won-Jae

    2006-01-01

    An elevated temperature structure design and analysis is one of the key issues in the VHTR (Very High Temperature Reactor) project to achieve an economic production of hydrogen which will be an essential energy source for the near future. Since the operating temperature of a VHTR is above 850 .deg. C, the existing code and standards are insufficient for a high temperature structure design. Thus the issues concerning a material selection and behaviors are being studied for the main structural components of a VHTR in leading countries such as US, France, UK, and Japan. In this study, the current status of the ASME code, French RCC-MR, UK R5, and Japanese code were investigated and the necessary R and D items were discussed

  14. On-line monitoring and inservice inspection in codes; Betriebsueberwachung und wiederkehrende Pruefungen in den Regelwerken

    Energy Technology Data Exchange (ETDEWEB)

    Bartonicek, J.; Zaiss, W. [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H.R. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany). Geschaeftsstelle des Kerntechnischen Ausschusses (KTA)

    1999-08-01

    The relevant regulatory codes determine the ISI tasks and the time intervals for recurrent components testing for evaluation of operation-induced damaging or ageing in order to ensure component integrity on the basis of the last available quality data. In-service quality monitoring is carried out through on-line monitoring and recurrent testing. The requirements defined by the engineering codes elaborated by various institutions are comparable, with the KTA nuclear engineering and safety codes being the most complete provisions for quality evaluation and assurance after different, defined service periods. German conventional codes for assuring component integrity provide exclusively for recurrent inspection regimes (mainly pressure tests and optical testing). The requirements defined in the KTA codes however always demanded more specific inspections relying on recurrent testing as well as on-line monitoring. Foreign codes for ensuring component integrity concentrate on NDE tasks at regular time intervals, with time intervals scope of testing activities being defined on the basis of the ASME code, section XI. (orig./CB) [Deutsch] Fuer die Komponentenintegritaet sind die Schaedigungsmechanismen mit dem nach den Regelwerken einzuhaltenden Abstand abzusichern. Dabei ist die jeweils vorhandene (Ist-) Qualitaet als Ausgangspunkt entscheidend. Die Absicherung der vorhandenen Qualitaet im weiteren Betrieb erfolgt durch geeignete Betriebsueberwachung und wiederkehrende Pruefungen. Die Anforderungen der Regelwerke sind vergleichbar, wobei die Bestimmung der vorhandenen Qualitaet nach einer bestimmten Betriebszeit sowie deren Absicherung im weiteren Betrieb am vollstaendigsten auf Basis des KTA-Regelwerkes moeglich ist. Die Absicherung der Komponentenintegritaet im Betrieb beruht in deutschen konventionellen Regelwerken nur auf den wiederkehrenden Pruefungen (hauptsaechlich Druckpruefungen und Sichtpruefungen). Das KTA-Regelwerk forderte hier schon immer qualifizierte

  15. 29 CFR Appendix A to Subpart S of... - References for Further Information

    Science.gov (United States)

    2010-07-01

    .... ANSI/ASME B30.8-2004 Floating Cranes And Floating Derricks. ANSI/ASME B30.11-2004 Monorails And... Different Bases. NFPA 20-2003 Standard for the Installation of Stationary Pumps for Fire Protection. NFPA 30...-2004.) NFPA 77-2000 Recommended Practice on Static Electricity. NFPA 80-1999 Standard for Fire Doors...

  16. Elaboration of data and documents intended to complement and expand the German series of nuclear engineering codes. 4. Technical report. Current knowledge of the mechanisms of corrosion fatigue in ferritic materials

    International Nuclear Information System (INIS)

    Frank, J.

    1997-01-01

    Concerning the processes of crack initiation under cyclic loading in a high-temperature water environment, examinations are performed in the USA for amending the design-basis curves published in ASME section III, which are comparable to those contained in the KTA code 3201.2. A revision of ASME section III has not yet been published. The same applies to the processes of crack propagation under cyclic loading in a high-temperature water environment, US experts examining for the purpose of amendment the limiting curves of cyclic crack propagation rates of carbon and low-alloyed steels in a water environment published in ASME section XI. (Orig./CB) [de

  17. ASM Based Synthesis of Handwritten Arabic Text Pages

    Directory of Open Access Journals (Sweden)

    Laslo Dinges

    2015-01-01

    Full Text Available Document analysis tasks, as text recognition, word spotting, or segmentation, are highly dependent on comprehensive and suitable databases for training and validation. However their generation is expensive in sense of labor and time. As a matter of fact, there is a lack of such databases, which complicates research and development. This is especially true for the case of Arabic handwriting recognition, that involves different preprocessing, segmentation, and recognition methods, which have individual demands on samples and ground truth. To bypass this problem, we present an efficient system that automatically turns Arabic Unicode text into synthetic images of handwritten documents and detailed ground truth. Active Shape Models (ASMs based on 28046 online samples were used for character synthesis and statistical properties were extracted from the IESK-arDB database to simulate baselines and word slant or skew. In the synthesis step ASM based representations are composed to words and text pages, smoothed by B-Spline interpolation and rendered considering writing speed and pen characteristics. Finally, we use the synthetic data to validate a segmentation method. An experimental comparison with the IESK-arDB database encourages to train and test document analysis related methods on synthetic samples, whenever no sufficient natural ground truthed data is available.

  18. ASM Based Synthesis of Handwritten Arabic Text Pages.

    Science.gov (United States)

    Dinges, Laslo; Al-Hamadi, Ayoub; Elzobi, Moftah; El-Etriby, Sherif; Ghoneim, Ahmed

    2015-01-01

    Document analysis tasks, as text recognition, word spotting, or segmentation, are highly dependent on comprehensive and suitable databases for training and validation. However their generation is expensive in sense of labor and time. As a matter of fact, there is a lack of such databases, which complicates research and development. This is especially true for the case of Arabic handwriting recognition, that involves different preprocessing, segmentation, and recognition methods, which have individual demands on samples and ground truth. To bypass this problem, we present an efficient system that automatically turns Arabic Unicode text into synthetic images of handwritten documents and detailed ground truth. Active Shape Models (ASMs) based on 28046 online samples were used for character synthesis and statistical properties were extracted from the IESK-arDB database to simulate baselines and word slant or skew. In the synthesis step ASM based representations are composed to words and text pages, smoothed by B-Spline interpolation and rendered considering writing speed and pen characteristics. Finally, we use the synthetic data to validate a segmentation method. An experimental comparison with the IESK-arDB database encourages to train and test document analysis related methods on synthetic samples, whenever no sufficient natural ground truthed data is available.

  19. 46 CFR 56.01-2 - Incorporation by reference.

    Science.gov (United States)

    2010-10-01

    ... Welded Ferritic and Martensitic Stainless Steel Tubing for General Service (“ASTM A 268”), 56.60-1; (21) ASTM A 276-98, Standard Specification for Stainless Steel Bars and Shapes (“ASTM A 276”), 56.60-2; (22... (27) ASME B36.19M-2004 Stainless Steel Pipe (2004) (“ASME B36.19M”), 56.07-5; 56.60-1. (28) ASME SA...

  20. Towards a consensus-based biokinetic model for green microalgae – The ASM-A

    DEFF Research Database (Denmark)

    Wágner, Dorottya Sarolta; Valverde Pérez, Borja; Sæbø, Mariann

    2016-01-01

    developed to predict microalgal growth. However, none of these models can effectively describe all the relevant processes when microalgal growth is coupled with nutrient removal and recovery from wastewaters. Here, we present a mathematical model developed to simulate green microalgal growth (ASM-A) using...... and substrate availability can introduce significant variability on parameter values for predicting the reaction rates for bulk nitrate and the intracellularly stored nitrogen state-variables, thereby requiring scenario specific model calibration. ASM-A was identified using standard cultivation medium...

  1. Application of adjusted subpixel method (ASM) in HRCT measurements of the bronchi in bronchial asthma patients and healthy individuals.

    Science.gov (United States)

    Mincewicz, Grzegorz; Rumiński, Jacek; Krzykowski, Grzegorz

    2012-02-01

    Recently, we described a model system which included corrections of high-resolution computed tomography (HRCT) bronchial measurements based on the adjusted subpixel method (ASM). To verify the clinical application of ASM by comparing bronchial measurements obtained by means of the traditional eye-driven method, subpixel method alone and ASM in a group comprised of bronchial asthma patients and healthy individuals. The study included 30 bronchial asthma patients and the control group comprised of 20 volunteers with no symptoms of asthma. The lowest internal and external diameters of the bronchial cross-sections (ID and ED) and their derivative parameters were determined in HRCT scans using: (1) traditional eye-driven method, (2) subpixel technique, and (3) ASM. In the case of the eye-driven method, lower ID values along with lower bronchial lumen area and its percentage ratio to total bronchial area were basic parameters that differed between asthma patients and healthy controls. In the case of the subpixel method and ASM, both groups were not significantly different in terms of ID. Significant differences were observed in values of ED and total bronchial area with both parameters being significantly higher in asthma patients. Compared to ASM, the eye-driven method overstated the values of ID and ED by about 30% and 10% respectively, while understating bronchial wall thickness by about 18%. Results obtained in this study suggest that the traditional eye-driven method of HRCT-based measurement of bronchial tree components probably overstates the degree of bronchial patency in asthma patients. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

  2. Application of adjusted subpixel method (ASM) in HRCT measurements of the bronchi in bronchial asthma patients and healthy individuals

    International Nuclear Information System (INIS)

    Mincewicz, Grzegorz; Rumiński, Jacek; Krzykowski, Grzegorz

    2012-01-01

    Background: Recently, we described a model system which included corrections of high-resolution computed tomography (HRCT) bronchial measurements based on the adjusted subpixel method (ASM). Objective: To verify the clinical application of ASM by comparing bronchial measurements obtained by means of the traditional eye-driven method, subpixel method alone and ASM in a group comprised of bronchial asthma patients and healthy individuals. Methods: The study included 30 bronchial asthma patients and the control group comprised of 20 volunteers with no symptoms of asthma. The lowest internal and external diameters of the bronchial cross-sections (ID and ED) and their derivative parameters were determined in HRCT scans using: (1) traditional eye-driven method, (2) subpixel technique, and (3) ASM. Results: In the case of the eye-driven method, lower ID values along with lower bronchial lumen area and its percentage ratio to total bronchial area were basic parameters that differed between asthma patients and healthy controls. In the case of the subpixel method and ASM, both groups were not significantly different in terms of ID. Significant differences were observed in values of ED and total bronchial area with both parameters being significantly higher in asthma patients. Compared to ASM, the eye-driven method overstated the values of ID and ED by about 30% and 10% respectively, while understating bronchial wall thickness by about 18%. Conclusions: Results obtained in this study suggest that the traditional eye-driven method of HRCT-based measurement of bronchial tree components probably overstates the degree of bronchial patency in asthma patients.

  3. Feature extraction for face recognition via Active Shape Model (ASM) and Active Appearance Model (AAM)

    Science.gov (United States)

    Iqtait, M.; Mohamad, F. S.; Mamat, M.

    2018-03-01

    Biometric is a pattern recognition system which is used for automatic recognition of persons based on characteristics and features of an individual. Face recognition with high recognition rate is still a challenging task and usually accomplished in three phases consisting of face detection, feature extraction, and expression classification. Precise and strong location of trait point is a complicated and difficult issue in face recognition. Cootes proposed a Multi Resolution Active Shape Models (ASM) algorithm, which could extract specified shape accurately and efficiently. Furthermore, as the improvement of ASM, Active Appearance Models algorithm (AAM) is proposed to extracts both shape and texture of specified object simultaneously. In this paper we give more details about the two algorithms and give the results of experiments, testing their performance on one dataset of faces. We found that the ASM is faster and gains more accurate trait point location than the AAM, but the AAM gains a better match to the texture.

  4. Twelfth annual conference of the CFD Society of Canada (CFD 2004). Proceedings

    International Nuclear Information System (INIS)

    Khalid, M.; Chen, S.; McIlwain, S.

    2004-01-01

    The Twelfth Annual Conference of the CFD Society of Canada, CFD 2004, was held in Ottawa, Ontario from May 9-11, 2004. The proceedings consists of 24 sessions covering the following topics: fluid structure interactions; multiphase and multi-species flows; mesh methods; turbulence; DNS/LES; supersonic and hypersonic flows; heat transfer; combustion and detonation; flow physics; aerodynamics; applications; algorithms; environmental flows; magnetohydrodynamics and electrohydrodynamics; biofluids; and, combustion and smoke management

  5. 3D automatic anatomy segmentation based on iterative graph-cut-ASM.

    Science.gov (United States)

    Chen, Xinjian; Bagci, Ulas

    2011-08-01

    This paper studies the feasibility of developing an automatic anatomy segmentation (AAS) system in clinical radiology and demonstrates its operation on clinical 3D images. The AAS system, the authors are developing consists of two main parts: object recognition and object delineation. As for recognition, a hierarchical 3D scale-based multiobject method is used for the multiobject recognition task, which incorporates intensity weighted ball-scale (b-scale) information into the active shape model (ASM). For object delineation, an iterative graph-cut-ASM (IGCASM) algorithm is proposed, which effectively combines the rich statistical shape information embodied in ASM with the globally optimal delineation capability of the GC method. The presented IGCASM algorithm is a 3D generalization of the 2D GC-ASM method that they proposed previously in Chen et al. [Proc. SPIE, 7259, 72590C1-72590C-8 (2009)]. The proposed methods are tested on two datasets comprised of images obtained from 20 patients (10 male and 10 female) of clinical abdominal CT scans, and 11 foot magnetic resonance imaging (MRI) scans. The test is for four organs (liver, left and right kidneys, and spleen) segmentation, five foot bones (calcaneus, tibia, cuboid, talus, and navicular). The recognition and delineation accuracies were evaluated separately. The recognition accuracy was evaluated in terms of translation, rotation, and scale (size) error. The delineation accuracy was evaluated in terms of true and false positive volume fractions (TPVF, FPVF). The efficiency of the delineation method was also evaluated on an Intel Pentium IV PC with a 3.4 GHZ CPU machine. The recognition accuracies in terms of translation, rotation, and scale error over all organs are about 8 mm, 10 degrees and 0.03, and over all foot bones are about 3.5709 mm, 0.35 degrees and 0.025, respectively. The accuracy of delineation over all organs for all subjects as expressed in TPVF and FPVF is 93.01% and 0.22%, and all foot bones for

  6. 3D automatic anatomy segmentation based on iterative graph-cut-ASM

    International Nuclear Information System (INIS)

    Chen, Xinjian; Bagci, Ulas

    2011-01-01

    Purpose: This paper studies the feasibility of developing an automatic anatomy segmentation (AAS) system in clinical radiology and demonstrates its operation on clinical 3D images. Methods: The AAS system, the authors are developing consists of two main parts: object recognition and object delineation. As for recognition, a hierarchical 3D scale-based multiobject method is used for the multiobject recognition task, which incorporates intensity weighted ball-scale (b-scale) information into the active shape model (ASM). For object delineation, an iterative graph-cut-ASM (IGCASM) algorithm is proposed, which effectively combines the rich statistical shape information embodied in ASM with the globally optimal delineation capability of the GC method. The presented IGCASM algorithm is a 3D generalization of the 2D GC-ASM method that they proposed previously in Chen et al.[Proc. SPIE, 7259, 72590C1-72590C-8 (2009)]. The proposed methods are tested on two datasets comprised of images obtained from 20 patients (10 male and 10 female) of clinical abdominal CT scans, and 11 foot magnetic resonance imaging (MRI) scans. The test is for four organs (liver, left and right kidneys, and spleen) segmentation, five foot bones (calcaneus, tibia, cuboid, talus, and navicular). The recognition and delineation accuracies were evaluated separately. The recognition accuracy was evaluated in terms of translation, rotation, and scale (size) error. The delineation accuracy was evaluated in terms of true and false positive volume fractions (TPVF, FPVF). The efficiency of the delineation method was also evaluated on an Intel Pentium IV PC with a 3.4 GHZ CPU machine. Results: The recognition accuracies in terms of translation, rotation, and scale error over all organs are about 8 mm, 10 deg. and 0.03, and over all foot bones are about 3.5709 mm, 0.35 deg. and 0.025, respectively. The accuracy of delineation over all organs for all subjects as expressed in TPVF and FPVF is 93.01% and 0.22%, and

  7. A novel anti-inflammatory drug, SDZ ASM 981, for the treatment of skin diseases: in vitro pharmacology.

    Science.gov (United States)

    Grassberger, M; Baumruker, T; Enz, A; Hiestand, P; Hultsch, T; Kalthoff, F; Schuler, W; Schulz, M; Werner, F J; Winiski, A; Wolff, B; Zenke, G

    1999-08-01

    SDZ ASM 981, a novel ascomycin macrolactam derivative, has high anti-inflammatory activity in animal models of allergic contact dermatitis and shows clinical efficacy in atopic dermatitis, allergic contact dermatitis and psoriasis, after topical application. Here we report on the in vitro activities of this promising new drug. SDZ ASM 981 inhibits the proliferation of human T cells after antigen-specific or non-specific stimulation. It downregulates the production of Th1 [interleukin (IL)-2, interferon-gamma] and Th2 (IL-4, IL-10) type cytokines after antigen-specific stimulation of a human T-helper cell clone isolated from the skin of an atopic dermatitis patient. SDZ ASM 981 inhibits the phorbol myristate acetate/phytohaemagglutinin-stimulated transcription of a reporter gene coupled to the human IL-2 promoter in the human T-cell line Jurkat and the IgE/antigen-mediated transcription of a reporter gene coupled to the human tumour necrosis factor (TNF)-alpha promoter in the murine mast-cell line CPII. It does not, however, affect the human TNF-alpha promoter controlled transcription of a reporter gene in a murine dendritic cell line (DC18 RGA) after stimulation via the FcgammaRIII receptor. SDZ ASM 981 also prevents the release of preformed pro-inflammatory mediators from mast cells, as shown in the murine cell line CPII after stimulation with IgE/antigen. In summary, these results demonstrate that SDZ ASM 981 is a specific inhibitor of the production of pro-inflammatory cytokines from T cells and mast cells in vitro.

  8. Accelerator system model (ASM): A unique tool in exploring accelerator driven transmutation technologies (ADTT) system trade space

    Energy Technology Data Exchange (ETDEWEB)

    Myers, T.J.; Favale, A.J.; Berwald, D.H.; Burger, E.C.; Paulson, C.C.; Peacock, M.A.; Piaszczyk, C.M.; Piechowiak, E.M.; Rathke, J.W. [Northrop Grumman Corp., Bethpage, NY (United States). Advanced Technology and Development Center

    1997-09-01

    To aid in the development and optimization of emerging Accelerator Driven Transmutation Technology (ADTT) concepts, the Northrop Grumman Corporation, working together with G.H. Gillespie Associates and Los Alamos National Laboratory has developed a computational tool which combines both accelerator physics layout/analysis capabilities with engineering analysis capabilities to create a standardized platform to compare and contrast accelerator system configurations. In this context, the accelerator system configuration includes not only the accelerating structures, but also the major support systems such as the vacuum, thermal control, RF power, and cryogenic subsystem (if superconducting accelerator operation is investigated) as well as estimates of the costs for enclosures (accelerating tunnel and RF halls). This paper presents an overview of the Accelerator System Model (ASM) code flow, as well as a discussion of the data and analysis upon which it is based. Also presented is material which addresses the development of the evaluation criteria employed by this code including a presentation of the economic analysis methods, and a discussion of the cost database employed. The paper concludes with examples depicting completed and planned trade studies for both normal and superconducting accelerator applications. 8 figs.

  9. ENSEIGNEMENT TECHNIQUE CERN 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Aimeriez-vous améliorer vos connaissances des applications de Microsoft Office ou d'Outlook ? Un nouveau cours, combinant un cours avec professeur et une formation multi-media sur ordinateur, est proposé par l'Enseignement Technique : Instructor-led CERN Web-based Technical Training (WBTechT) Course for Microsoft Applications. La prochaine session aura lieu le 1er avril 2004 matin. Ces sessions sont de forme "auto-formation", les participants étant autonomes tout en ayant accès au soutien du professeur lorsqu'ils sont dans la salle de cours. Les sujets proposés sont les applications de Microsoft Office XP (Word, Excel, PowerPoint, Access) ainsi qu'Outlook, déclinés aux niveaux introduction, intermédiaire et avancé. Consultez le portail 2004 CERN WBTechT, où vous trouverez le contenu détaillé des cours du catalogue "Microsoft Office XP". Aucune expérience préalable en auto-formation utilisant le Web n'est nécessaire : chaque session débutera par une introduction à l'E-formation et par l'insc...

  10. ASME Evaluation on Grid Mobile E-Commerce Process

    OpenAIRE

    Dan Chang; Wei Liao

    2012-01-01

    With the development of E-commerce, more scholars have paid attention to research on Mobile E-commerce and mostly focus on the optimization and evaluation of existing process. This paper researches the evaluation of Mobile E-commerce process with a method called ASME. Based on combing and analyzing current mobile business process and utilizing the grid management theory, mobile business process based on grid are constructed. Firstly, the existing process, namely Non-grid Mobile E-commerce, an...

  11. Conservatism of ASME KIR-reference curve with respect to crack arrest

    International Nuclear Information System (INIS)

    Wallin, K.; Rintamaa, R.; Nagel, G.

    1999-01-01

    The conservatism of the RT NDT temperature indexing parameter and the ASME K IR -reference curve with respect to crack arrest toughness, has been evaluated. Based on an analysis of the original ASME K Ia data, it was established that inherently, the ASME K IR -reference curve corresponds to an overall 5% lower bound curve with respect to crack arrest. It was shown that the scatter of crack arrest toughness is essentially material independent and has a standard deviation of 18% and the temperature dependence of K Ia has the same form as predicted by the master curve for crack initiation toughness. The 'built in' offset between the mean 100 MPa√(m) crack arrest temperature, TK Ia , and RT NDT is 38 C (TK Ia =RT NDT +38 C) and the experimental relation between TK Ia and NDT is, TK Ia =NDT+28 C. The K IR -reference curve using NDT as reference temperature will be conservative with respect to the general 5% lower bound K Ia(5%) -curve, with a 75% confidence. The use of RT NDT , instead of NDT, will generally increase the degree of conservatism, both for non-irradiated as well as irradiated materials, close to a 95% confidence level. This trend is pronounced for materials with Charpy-V upper shelf energies below 100 J. It is shown that the K IR -curve effectively constitutes a deterministic lower bound curve for crack arrest. The findings are valid both for nuclear pressure vessel plates, forgings and welds. (orig.)

  12. Conservatism of ASME KIR-reference curve with respect to crack arrest

    International Nuclear Information System (INIS)

    Wallin, K.; Rintamaa, R.; Nagel, G.

    2001-01-01

    The conservatism of the RT NDT temperature indexing parameter and the ASME K IR -reference curve with respect to crack arrest toughness, has been evaluated. Based on an analysis of the original ASME K Ia data, it was established that inherently, the ASME K IR -reference curve corresponds to an overall 5% lower bound curve with respect to crack arrest. It was shown that the scatter of crack arrest toughness is essentially material independent and has a standard deviation (S.D.) of 18% and the temperature dependence of K Ia has the same form as predicted by the master curve for crack initiation toughness. The 'built in' offset between the mean 100 MPa√m crack arrest temperature, TK Ia , and RT NDT is 38 deg. C (TK Ia =RT NDT +38 deg. C) and the experimental relation between TK Ia and NDT is, TK Ia =NDT+28 deg. C. The K IR -reference curve using NDT as reference temperature will be conservative with respect to the general 5% lower bound K Ia(5%) -curve, with a 75% confidence. The use of RT NDT , instead of NDT, will generally increase the degree of conservatism, both for non-irradiated as well as irradiated materials, close to a 95% confidence level. This trend is pronounced for materials with Charpy-V upper shelf energies below 100 J. It is shown that the K IR -curve effectively constitutes a deterministic lower bound curve for crack arrest The findings are valid both for nuclear pressure vessel plates, forgings and welds

  13. Forum Engelberg, 1-4 March 2004

    CERN Document Server

    2004-01-01

    The 2004 Forum Engelberg will pay tribute to its President, Hubert Curien, a former President of the CERN Council and former French Minister for Research. The subject of this year's conference, which will take place in Lucerne from 1st to 4th March 2004, is "Science on the Agenda of European Politics." This year, there will be talks by numerous speakers, including the directors of the seven European intergovernmental scientific organisations (EIROforum) and the European Commissioner for Research, Philippe Busquin. The highlights of the conference will include an Interdisciplinary Scientific Programme on 2nd and 3rd March, a session on e-science and the Grid on 4th March and a Young Scientists Programme. The programme and registration forms are available at http://www.forum-engelberg.org/

  14. Energy and Power Measurements for Network Coding in the Context of Green Mobile Clouds

    DEFF Research Database (Denmark)

    Paramanathan, Achuthan; Pedersen, Morten Videbæk; Roetter, Daniel Enrique Lucani

    2013-01-01

    results for inter-session network coding in Open-Mesh routers underline that the energy invested in performing network coding pays off by dramatically reducing the total energy for the transmission of data over wireless links. We also show measurements for intra-session network coding in three different......This paper presents an in-depth power and energy measurement campaign for inter- and intra-session network coding enabled communication in mobile clouds. The measurements are carried out on different commercial platforms with focus on routers and mobile phones with different CPU capabilities. Our...

  15. DOE Hydrogen Program 2004 Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    2004-10-01

    This document summarizes the project evaluations and comments from the DOE Hydrogen Program 2004 Annual Program Review. Hydrogen production, delivery and storage; fuel cells; technology validation; safety, codes and standards; and education R&D projects funded by DOE in FY2004 are reviewed.

  16. Statistical analysis of geomagnetic field intensity differences between ASM and VFM instruments onboard Swarm constellation

    Science.gov (United States)

    De Michelis, Paola; Tozzi, Roberta; Consolini, Giuseppe

    2017-02-01

    From the very first measurements made by the magnetometers onboard Swarm satellites launched by European Space Agency (ESA) in late 2013, it emerged a discrepancy between scalar and vector measurements. An accurate analysis of this phenomenon brought to build an empirical model of the disturbance, highly correlated with the Sun incidence angle, and to correct vector data accordingly. The empirical model adopted by ESA results in a significant decrease in the amplitude of the disturbance affecting VFM measurements so greatly improving the vector magnetic data quality. This study is focused on the characterization of the difference between magnetic field intensity measured by the absolute scalar magnetometer (ASM) and that reconstructed using the vector field magnetometer (VFM) installed on Swarm constellation. Applying empirical mode decomposition method, we find the intrinsic mode functions (IMFs) associated with ASM-VFM total intensity differences obtained with data both uncorrected and corrected for the disturbance correlated with the Sun incidence angle. Surprisingly, no differences are found in the nature of the IMFs embedded in the analyzed signals, being these IMFs characterized by the same dominant periodicities before and after correction. The effect of correction manifests in the decrease in the energy associated with some IMFs contributing to corrected data. Some IMFs identified by analyzing the ASM-VFM intensity discrepancy are characterized by the same dominant periodicities of those obtained by analyzing the temperature fluctuations of the VFM electronic unit. Thus, the disturbance correlated with the Sun incidence angle could be still present in the corrected magnetic data. Furthermore, the ASM-VFM total intensity difference and the VFM electronic unit temperature display a maximal shared information with a time delay that depends on local time. Taken together, these findings may help to relate the features of the observed VFM-ASM total intensity

  17. Simulation of municipal-industrial full scale WWTP in an arid climate by application of ASM3

    Directory of Open Access Journals (Sweden)

    Abdelsalam Elawwad

    2017-03-01

    Full Text Available In developing countries, and due to the high cost of treatment of industrial wastewater, municipal wastewater treatment facilities usually receive a mixture of municipal wastewater and partially treated industrial wastewater. As a result, an increased potential for shock loads with high pollutant concentrations is expected. The use of mathematical modelling of wastewater treatment is highly efficient in such cases. A dynamic model based on activated sludge model no. 3 (ASM3 describing the performance of the activated sludge process at a full scale wastewater treatment plant (WWTP receiving mixed domestic–industrial wastewater located in an arid area is presented. ASM3 was extended by adding the Arrhenius equation to respond to changes in temperature. BioWin software V.4 was used as the model platform. The model was calibrated under steady-state conditions, adjusting only three kinetic and stoichiometric parameters: maximum heterotrophic growth rate (μH = 8 d−1, heterotrophic aerobic decay rate (bH, O2 = 0.18 d−1, and aerobic heterotrophic yield (YH,O2 = 0.4 (gCOD/gCOD. ASM3 was successful in predicting the WWTP performance, as the model was validated with 10 months of routine daily measurements. ASM3 extended with the Arrhenius equation could be helpful in the design and operation of WWTPs with mixed municipal–industrial influent in arid areas.

  18. Proceedings of the European Symposium on Pressure Equipment - ESOPE 2007

    International Nuclear Information System (INIS)

    2007-01-01

    Every three years, and since thirty years, the AFIAP organizes a symposium where the experts and actors working in the field of pressure equipments, whether fixed or transportable, can meet and exchange on all developments related to their activity. What was at first called the 'National Congress on the technology of pressure components', and later the 'Study Days on pressure components', became since 2001 the 'European Symposium on Pressure Equipment' (ESOPE), so marking an opening to the European and International fields in a context marked by the application of the European Directives applicable to these equipments. The 2001 symposium was more particularly dedicated to the application of the directives harmonizing the construction of equipments, and the 2004 symposium was more particularly centred on the management of equipments in operation. For the ESOPE 2007 Symposium, the organizing committee wished to resume these two subjects under the aspects of the safety, the competitiveness, as well as the innovation. The plenary session of the last day will be completely dedicated to these subjects and will include a Panel discussion, where National and European authorities, representatives of manufacturers and users, as well as experts engaged in developments and new projects will express their views. These exchanges will also permit to answer the questions expressed by the participants. Every symposium has thus a main orientation, but shall also be the place of exchanges on the different subjects wished by the profession. The traditional technical sessions are consequently maintained: - Sessions on Design and Materials, - Sessions on Fabrication, - Sessions on Fitness for Service, and a special session dedicated to the National, European and International Codes is added, the afternoon of the first day. The plenary Opening session is also devoted to this last subject with lectures on the evolutions of European regulations, the orientations retained for pressure

  19. IM (Integrity Management) software must show flexibility to local codes

    Energy Technology Data Exchange (ETDEWEB)

    Brors, Markus [ROSEN Technology and Research Center GmbH (Germany); Diggory, Ian [Macaw Engineering Ltd., Northumberland (United Kingdom)

    2009-07-01

    There are many internationally recognized codes and standards, such as API 1160 and ASME B31.8S, which help pipeline operators to manage and maintain the integrity of their pipeline networks. However, operators in many countries still use local codes that often reflect the history of pipeline developments in their region and are based on direct experience and research on their pipelines. As pipeline companies come under increasing regulatory and financial pressures to maintain the integrity of their networks, it is important that operators using regional codes are able to benchmark their integrity management schemes against these international standards. Any comprehensive Pipeline Integrity Management System (PIMS) software package should therefore not only incorporate industry standards for pipeline integrity assessment but also be capable of implementing regional codes for comparison purposes. This paper describes the challenges and benefits of incorporating one such set of regional pipeline standards into ROSEN Asset Integrity Management Software (ROAIMS). (author)

  20. FOREN 2004. Sustainable Energy Development and European Integration

    International Nuclear Information System (INIS)

    Iancu Iulian

    2004-01-01

    The 7th Regional Energy Forum- FOREN 2004 with the main topic 'Sustainable Energy Development and European Integration' took place in Neptun-Olimp, on 13th to 17th June 2004. The event was organized by WEC Romanian National Committee, under the auspices of the World Energy Council (WEC). The event was accompanied by several related manifestation as: An up to date Technical Programme designed to explore key issues concerning the ability of the Romanian energy industry to integrate in the European Union; An Exhibition providing first hand access to service and equipment providers; A Partnership Programme, to present the achievements and developments of power companies in round tables, film projections, technical visits and advertising; Social events giving to participants the opportunity to establish direct connections with the Romanian colleagues. The Forum was open to members of the World Energy Council, energy industry leaders, government ministers and officials, heads of international organizations like: UNECE, EC, IEA, Eurelectric, IGU, EUROgas, USAID, academics, media, individual and corporate members interested in sustainable energy development. For further details concerning the agenda and registration. Forum 2004 was structured on five sections each containing a key issue a panel session, communication session and poster presentation on the following items: 1. Energy legislation and institutional framework; 2. The technological dimension of sustainable energy; 3. The ecological dimension of sustainable development; 4. The social dimension of sustainable development; 5. The power equipment manufacturing industry

  1. Spectrum of SMPD1 mutations in Asian-Indian patients with acid sphingomyelinase (ASM)-deficient Niemann-Pick disease.

    Science.gov (United States)

    Ranganath, Prajnya; Matta, Divya; Bhavani, Gandham SriLakshmi; Wangnekar, Savita; Jain, Jamal Mohammed Nurul; Verma, Ishwar C; Kabra, Madhulika; Puri, Ratna Dua; Danda, Sumita; Gupta, Neerja; Girisha, Katta M; Sankar, Vaikom H; Patil, Siddaramappa J; Ramadevi, Akella Radha; Bhat, Meenakshi; Gowrishankar, Kalpana; Mandal, Kausik; Aggarwal, Shagun; Tamhankar, Parag Mohan; Tilak, Preetha; Phadke, Shubha R; Dalal, Ashwin

    2016-10-01

    Acid sphingomyelinase (ASM)-deficient Niemann-Pick disease is an autosomal recessive lysosomal storage disorder caused by biallelic mutations in the SMPD1 gene. To date, around 185 mutations have been reported in patients with ASM-deficient NPD world-wide, but the mutation spectrum of this disease in India has not yet been reported. The aim of this study was to ascertain the mutation profile in Indian patients with ASM-deficient NPD. We sequenced SMPD1 in 60 unrelated families affected with ASM-deficient NPD. A total of 45 distinct pathogenic sequence variants were found, of which 14 were known and 31 were novel. The variants included 30 missense, 4 nonsense, and 9 frameshift (7 single base deletions and 2 single base insertions) mutations, 1 indel, and 1 intronic duplication. The pathogenicity of the novel mutations was inferred with the help of the mutation prediction software MutationTaster, SIFT, Polyphen-2, PROVEAN, and HANSA. The effects of the identified sequence variants on the protein structure were studied using the structure modeled with the help of the SWISS-MODEL workspace program. The p. (Arg542*) (c.1624C>T) mutation was the most commonly identified mutation, found in 22% (26 out of 120) of the alleles tested, but haplotype analysis for this mutation did not identify a founder effect for the Indian population. To the best of our knowledge, this is the largest study on mutation analysis of patients with ASM-deficient Niemann-Pick disease reported in literature and also the first study on the SMPD1 gene mutation spectrum in India. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  2. Citations of plenary-session articles published in the Proceedings of the International Symposium on Veterinary Epidemiology and Economics.

    Science.gov (United States)

    Salman, M D; Dewell, Reneé; Willeberg, Preben; GrandMaison, Nadine; Schoenbaum, Melissa; Moothart, Tom

    2007-06-15

    We measured the potential impact of articles representing the International Symposium on Veterinary Epidemiology and Economics (ISVEE) plenary-session presentations in subsequent published literature. Between July 1, 2004 and November 9, 2004, we searched the Web of Science for citations in the scientific literature to all 99 plenary-session articles published in the proceedings of the previous nine ISVEEs (or in journal special issues dedicated to the ISVEE plenary articles). We used a 4-year window around the publication of each of the ISVEE proceedings. We located 187 citations for 37 (of the 99) articles. We infer that the ISVEE proceedings represent an important resource for veterinary epidemiology.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

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

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

    International Nuclear Information System (INIS)

    Spaeh, Peter; Aiello, Gaetano; Gagliardi, Mario; Grossetti, Giovanni; Meier, Andreas; Scherer, Theo; Schreck, Sabine; Strauss, Dirk; Vaccaro, Alessandro; Weinhorst, Bastian

    2015-01-01

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

  5. Ideas for Advancing Code Sharing: A Different Kind of Hack Day

    Science.gov (United States)

    Teuben, P.; Allen, A.; Berriman, B.; DuPrie, K.; Hanisch, R. J.; Mink, J.; Nemiroff, R. J.; Shamir, L.; Shortridge, K.; Taylor, M. B.; Wallin, J. F.

    2014-05-01

    How do we as a community encourage the reuse of software for telescope operations, data processing, and ? How can we support making codes used in research available for others to examine? Continuing the discussion from last year Bring out your codes! BoF session, participants separated into groups to brainstorm ideas to mitigate factors which inhibit code sharing and nurture those which encourage code sharing. The BoF concluded with the sharing of ideas that arose from the brainstorming sessions and a brief summary by the moderator.

  6. Flujo espiratorio máximo en niños asmáticos: Casos y controles

    Directory of Open Access Journals (Sweden)

    Arturo Recabarren Lozada

    1995-04-01

    Full Text Available Con el fin de determinar las variaciones del Flujo Espiratorio Máximo (PEF, se estudiaron a 38 niños asmáticos (CASOS en período intercrítico de la enfermedad y a 38 niños sanos (CONTROLES, de ambos sexos comprendidos entre los 5 y 15 años de edad. Los niños asmáticos fueron clasificados por parámetros clínicos en determinado grado de severidad de asma bronquial, determinando el PEF de cada niño objeto de estudio conel mini-Wright Peak Flow Meter, en 2 registros diarios a los 06 y 18 horas, durante 7 días consecutivos, obteniendo la variabilidad del mismo. Se encuentra diferencia en la variabilidad global de niños asmáticos de todos los grados de severidad de la enfermedad comprada con la de los niños normales, con diferencia estadística altamente significativa (p<0.000001. Las variaciones diurnas del PEF ayuda en el diagnóstico del asma bronquial y también son útiles para realizar la catalogación de severidad de la enfermedad. El PEF correlaciona bien con los síntomas presentados por los pacientes y por lo tanto guarda correspondencia con la Hiperreactividad bronquial (HRB del niño asmático. Postulamos que un niño con historia clínica sugestiva, una variabilidad global mayor del 8% indica que el diagnóstico de asma es altamente probable (Rev Med Hered 1995; 6: 76-82

  7. From In-Session Behaviors to Drinking Outcomes: A Causal Chain for Motivational Interviewing

    Science.gov (United States)

    Moyers, Theresa B.; Martin, Tim; Houck, Jon M.; Christopher, Paulette J.; Tonigan, J. Scott

    2009-01-01

    Client speech in favor of change within motivational interviewing sessions has been linked to treatment outcomes, but a causal chain has not yet been demonstrated. Using a sequential behavioral coding system for client speech, the authors found that, at both the session and utterance levels, specific therapist behaviors predict client change talk.…

  8. Statistical re-evaluation of the ASME KIC and KIR fracture toughness reference curves

    International Nuclear Information System (INIS)

    Wallin, K.

    1999-01-01

    Historically the ASME reference curves have been treated as representing absolute deterministic lower bound curves of fracture toughness. In reality, this is not the case. They represent only deterministic lower bound curves to a specific set of data, which represent a certain probability range. A recently developed statistical lower bound estimation method called the 'master curve', has been proposed as a candidate for a new lower bound reference curve concept. From a regulatory point of view, the master curve is somewhat problematic in that it does not claim to be an absolute deterministic lower bound, but corresponds to a specific theoretical failure probability that can be chosen freely based on application. In order to be able to substitute the old ASME reference curves with lower bound curves based on the master curve concept, the inherent statistical nature (and confidence level) of the ASME reference curves must be revealed. In order to estimate the true inherent level of safety, represented by the reference curves, the original database was re-evaluated with statistical methods and compared to an analysis based on the master curve concept. The analysis reveals that the 5% lower bound master curve has the same inherent degree of safety as originally intended for the K IC -reference curve. Similarly, the 1% lower bound master curve corresponds to the K IR -reference curve. (orig.)

  9. Statistical re-evaluation of the ASME KIC and KIR fracture toughness reference curves

    International Nuclear Information System (INIS)

    Wallin, K.; Rintamaa, R.

    1998-01-01

    Historically the ASME reference curves have been treated as representing absolute deterministic lower bound curves of fracture toughness. In reality, this is not the case. They represent only deterministic lower bound curves to a specific set of data, which represent a certain probability range. A recently developed statistical lower bound estimation method called the 'Master curve', has been proposed as a candidate for a new lower bound reference curve concept. From a regulatory point of view, the Master curve is somewhat problematic in that it does not claim to be an absolute deterministic lower bound, but corresponds to a specific theoretical failure probability that can be chosen freely based on application. In order to be able to substitute the old ASME reference curves with lower bound curves based on the master curve concept, the inherent statistical nature (and confidence level) of the ASME reference curves must be revealed. In order to estimate the true inherent level of safety, represented by the reference curves, the original data base was re-evaluated with statistical methods and compared to an analysis based on the master curve concept. The analysis reveals that the 5% lower bound Master curve has the same inherent degree of safety as originally intended for the K IC -reference curve. Similarly, the 1% lower bound Master curve corresponds to the K IR -reference curve. (orig.)

  10. Effects of ASM-024, a modulator of acetylcholine receptor function, on airway responsiveness and allergen-induced responses in patients with mild asthma.

    Science.gov (United States)

    Boulet, Louis-Philippe; Gauvreau, Gail M; Cockcroft, Donald W; Davis, Beth; Vachon, Luc; Cormier, Yvon; O'Byrne, Paul M

    2015-01-01

    To evaluate the safety, tolerability and clinical activity of ASM-024, a new cholinergic compound with dual nicotinic and muscarinic activity, in mild allergic asthma. The present study involved 24 stable, mild allergic asthmatic subjects. In a cross-over design, ASM-024 (50 mg or 200 mg) or placebo were administered once daily by nebulization over three periods of nine consecutive days separated by a three-week washout. The effect of each treatment on the forced expiratory volume in 1 s (FEV1), provocative concentration of methacholine causing a 20% decline in FEV1 (PC20), early and late asthmatic responses, and allergen-induced inflammation were measured. Seventeen subjects completed the study. During treatment with ASM-024 at 50 mg or 200 mg, the PC20 value increased respectively from a mean (± SD) 2.56±3.86 mg/mL to 4.11 mg/mL (P=0.007), and from 3.12±4.37 mg/mL to 5.23 mg/mL (P=0.005) (no change with placebo). On day 7 (day preceding allergen challenge), postdosing FEV1 increased by 2.0% with 50 mg (P=0.005) and 1.9% with 200 mg (P=0.008) (placebo -1.1%). ASM-24 had no inhibitory effect on early and late asthmatic responses, nor on sputum eosinophil or neutrophil levels. ASM-024 induced no serious adverse events, but caused cough in 22% and 48% of the subjects with 50 mg and 200 mg, respectively, compared with 10% who were on placebo. ASM-024 did not inhibit allergen-induced asthmatic response and related airway inflammation, but reduced methacholine airway responsiveness and slightly improved lung function. The mechanism by which ASM-024 improves these outcomes requires further study.

  11. IL-17A acts via p38 MAPK to increase stability of TNF-alpha-induced IL-8 mRNA in human ASM.

    Science.gov (United States)

    Henness, Sheridan; van Thoor, Eveline; Ge, Qi; Armour, Carol L; Hughes, J Margaret; Ammit, Alaina J

    2006-06-01

    Human airway smooth muscle (ASM) plays an immunomodulatory role in asthma. Recently, IL-17A has become of increasing interest in asthma, being found at elevated levels in asthmatic airways and emerging as playing an important role in airway neutrophilia. IL-17A predominantly exerts its neutrophil orchestrating role indirectly via the induction of cytokines by resident airway structural cells. Here, we perform an in vitro study to show that although IL-17A did not induce secretion of the CXC chemokine IL-8 from ASM cells, IL-17A significantly potentiates TNF-alpha-induced IL-8 protein secretion and gene expression in a concentration- and time-dependent manner (P ASM cells, acting via a p38 MAPK-dependent posttranscriptional pathway to augment TNF-alpha-induced secretion of the potent neutrophil chemoattractant IL-8 from ASM cells.

  12. Understanding the Long-Term Spectral Variability of Cygnus X-1 from BATSE and ASM Observations

    Science.gov (United States)

    Zdziarski, Andrzej A.; Poutanen, Juri; Paciesas, William S.; Wen, Linqing; Six, N. Frank (Technical Monitor)

    2002-01-01

    We present a spectral analysis of observations of Cygnus X-1 by the RXTE/ASM (1.5-12 keV) and CGRO/BATSE (20-300 keV), including about 1200 days of simultaneous data. We find a number of correlations between intensities and hardnesses in different energy bands from 1.5 keV to 300 keV. In the hard (low) spectral state, there is a negative correlation between the ASM 1.5-12 keV flux and the hardness at any energy. In the soft (high) spectral state, the ASM flux is positively correlated with the ASM hardness (as previously reported) but uncorrelated with the BATSE hardness. In both spectral states, the BATSE hardness correlates with the flux above 100 keV, while it shows no correlation with the flux in the 20-100 keV range. At the same time, there is clear correlation between the BATSE fluxes below and above 100 keV. In the hard state, most of the variability can be explained by softening the overall spectrum with a pivot at approximately 50 keV. The observations show that there has to be another, independent variability pattern of lower amplitude where the spectral shape does not change when the luminosity changes. In the soft state, the variability is mostly caused by a variable hard (Comptonized) spectral component of a constant shape superimposed on a constant soft blackbody component. These variability patterns are in agreement with the dependence of the rms variability on the photon energy in the two states. We interpret the observed correlations in terms of theoretical Comptonization models. In the hard state, the variability appears to be driven mostly by changing flux in seed photons Comptonized in a hot thermal plasma cloud with an approximately constant power supply. In the soft state, the variability is consistent with flares of hybrid, thermal/nonthermal, plasma with variable power above a stable cold disk. Also, based on broadband pointed observations simultaneous with those of the ASM and BATSE, we find the intrinsic bolometric luminosity increases by a

  13. More on fatigue verification of Class 1 nuclear power piping according to ASME BPV III NB-3600

    International Nuclear Information System (INIS)

    Zeng, Lingfu; Dahlström, Lars; Jansson, Lennart G.

    2011-01-01

    In this paper, fatigue verification of Class 1 nuclear power piping according to ASME Boiler and Pressure Vessel Code, Section III, NB-3600, and relevant issues that are often discussed in connection to the power uprate of several Swedish BWR reactors in recent years, are dealt with. Key parameters involved in the fatigue verification, i.e. the alternating stress intensity S alt , the penalty factor K e and the cumulative damage factor U, and relevant computational procedures applicable for the assessment of low-cycle fatigue failure using strain-controlled data, are particularly addressed. A so-called simplified elastic-plastic discontinuity analysis for alternative verification when basic fatigue requirements found unsatisfactory, and the procedures provided in NB-3600 for evaluating the alternating stress intensity S alt , are reviewed in detail. Our emphasis is placed on other procedures alternative to the simplified elastic-plastic discontinuity analysis. A more in-depth discussion is given to an alternative suggested earlier by the authors using nonlinear finite element analyses. This paper is a continuation of our work presented in ICONE16/17/18, which attempted to categorize design rules in the code into linear design rules and non-linear design rules and to clarify corresponding design requirements and finite element analyses, in particular, those non-linear ones. (author)

  14. Iterative and non-iterative solutions of engine flows using ASM and k-ε turbulence models

    International Nuclear Information System (INIS)

    Khaleghi, H.; Fallah, E.

    2003-01-01

    Various turbulent models are widely developed in order to make a good prediction of turbulence phenomena in different applications. The standard k-ε model shows a poor prediction for some applications. The Reynolds Stress Model (RSM) is expected to give a better prediction of turbulent characteristics, because a separate differential equation for each Reynolds stress component is solved in this model. In order to save both time and memory in this calculation a new Algebraic Stress Model (ASM) which was developed by Lumly et al in 1995 is used for calculations of flow characteristics in the internal combustion engine chamber. With using turbulent realizability principles, this model becomes a powerful and reliable turbulence model. In this paper the abilities of the model is examined in internal combustion engine flows. The results of ASM and k-ε models are compared with the experimental data. It is shown that the poor predictions of k-ε model are modified by ASM model. Also in this paper non-iterative PISO and iterative SIMPLE solution algorithms are compared. The results show that the PISO solution algorithm is the preferred and more efficient procedure in the calculation of internal combustion engine. (author)

  15. Measuring coding intensity in the Medicare Advantage program.

    Science.gov (United States)

    Kronick, Richard; Welch, W Pete

    2014-01-01

    In 2004, Medicare implemented a system of paying Medicare Advantage (MA) plans that gave them greater incentive than fee-for-service (FFS) providers to report diagnoses. Risk scores for all Medicare beneficiaries 2004-2013 and Medicare Current Beneficiary Survey (MCBS) data, 2006-2011. Change in average risk score for all enrollees and for stayers (beneficiaries who were in either FFS or MA for two consecutive years). Prevalence rates by Hierarchical Condition Category (HCC). Each year the average MA risk score increased faster than the average FFS score. Using the risk adjustment model in place in 2004, the average MA score as a ratio of the average FFS score would have increased from 90% in 2004 to 109% in 2013. Using the model partially implemented in 2014, the ratio would have increased from 88% to 102%. The increase in relative MA scores appears to largely reflect changes in diagnostic coding, not real increases in the morbidity of MA enrollees. In survey-based data for 2006-2011, the MA-FFS ratio of risk scores remained roughly constant at 96%. Intensity of coding varies widely by contract, with some contracts coding very similarly to FFS and others coding much more intensely than the MA average. Underpinning this relative growth in scores is particularly rapid relative growth in a subset of HCCs. Medicare has taken significant steps to mitigate the effects of coding intensity in MA, including implementing a 3.4% coding intensity adjustment in 2010 and revising the risk adjustment model in 2013 and 2014. Given the continuous relative increase in the average MA risk score, further policy changes will likely be necessary.

  16. SDZ ASM 981: an emerging safe and effective treatment for atopic dermatitis.

    NARCIS (Netherlands)

    Luger, T.; Leent, E.J. van; Graeber, M.; Hedgecock, S.; Thurston, M.; Kandra, A.; Berth-Jones, J.; Bjerke, J.; Christophers, E.; Knop, J.; Knulst, A.C.; Morren, M.; Morris, A.; Reitamo, S.; Roed-Petersen, J.; Schoepf, E.; Thestrup-Pedersen, K.; Valk, P.G.M. van der; Bos, J.D.

    2001-01-01

    BACKGROUND: SDZ ASM 981 is a selective inhibitor of the production of pro-inflammatory cytokines from T cells and mast cells in vitro. It is the first ascomycin macrolactam derivative under development for the treatment of inflammatory skin diseases. OBJECTIVES: This study was designed to determine

  17. SDZ ASM 981: an emerging safe and effective treatment for atopic dermatitis

    NARCIS (Netherlands)

    Luger, T; Van Leent, EJM; Graeber, M; Hedgecock, S; Thurston, M; Kandra, A; Berth-Jones, J; Bjerke, J; Christophers, E; Knulst, AC; Morren, M; Morris, A; Reitamo, S; Roed-Petersen, J; Schoepf, E; Thestrup-Pedersen, K; van der Valk, P. G. M.; Bos, JD

    Background SDZ ASM 981 is a selective inhibitor of the production of pro-inflammatory cytokines from T cells and mast cells in vitro. It is the first ascomycin macrolactam derivative under development for the treatment of inflammatory skin diseases. Objectives This study was: designed to determine

  18. Summary of Technical Sessions - Summary and Recommendations

    International Nuclear Information System (INIS)

    2013-01-01

    Technical Session 1 - Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches dealing with Best Estimate codes and uncertainties evaluations. Existing methods were summarized and different papers were focused on specific methods stressing their bases, peculiarities, advantages and limitations. As a result of the session a picture of the current State of the Art was obtained. The session comprised six papers. Technical Session 2 - International comparative activities: This session had as a main objective to review the activities launched in the past and present from the NEA in connection with BEPU methods, with focus on the applicability of conclusions derived from former benchmarks like UMS, the main outcomes of the recently finished BEMUSE project, and the objectives and relevance of UAM and PREMIUM projects. The session comprised four papers. Technical Session 3 - Applications: Licensing, safety analysis support, regulatory body views and industry activities: This session focused on the application of current methods in safety analyses. Contributions from industry, technical safety organizations and regulatory bodies were provided. As a result, a view of the penetration of BEPU methods in current safety analyses was obtained, as well as an indication of the evolution in the near future. Elements such as licensing practices, assessment process, etc. were considered. The session comprised nine papers. Technical Session 4. BEPU methods extension to new fields The session addressed the extension of BEPU methods beyond their current use. By now such methods are mainly applied to classic deterministic environment but it is believed that their benefits could be extended to other fields. Seven papers were presented in the session dealing with subjects that fit in the objectives established in the workshop programme. The papers cover areas like: extension to CFD, quantification of global safety

  19. Design and test of ASME strainer for primary cooling system in HANARO

    International Nuclear Information System (INIS)

    Park, Yong-Chul; Ryu, Jeong-Soo

    1999-01-01

    The ASME strainers have been newly installed at the suction side of each reactor coolant pump to get rid of the foreign materials which may damage the pump impeller or interfere with the coolant path of fuel flow tube or primary plate type heat exchanger. The strainer was designed in accordance with ASME SEC. III, DIV. 1, ND and the structural integrity was verified by seismic analysis. The screen was designed in accordance with the effective void area from the result of flow analysis for T-type strainer. After installation of the strainer, it was confirmed through the field test that the flow characteristics of primary cooling system were not adversely affected. The pressure loss coefficient was calculated by Darcy equation using the pressure difference through each strainer and the flow rate measured during the strainer performance test. And these are useful data to predict flow variations by the pressure difference. (author)

  20. When a Plant Resistance Inducer Leaves the Lab for the Field: Integrating ASM into Routine Apple Protection Practices.

    Science.gov (United States)

    Marolleau, Brice; Gaucher, Matthieu; Heintz, Christelle; Degrave, Alexandre; Warneys, Romain; Orain, Gilles; Lemarquand, Arnaud; Brisset, Marie-Noëlle

    2017-01-01

    Plant resistance inducers, also called elicitors, could be useful to reduce the use of pesticides. However, their performance in controlling diseases in the field remains unsatisfactory due to lack of specific knowledge of how they can integrate crop protection practices. In this work, we focused on apple crop and acibenzolar- S -methyl (ASM), a well-known SAR (systemic acquired resistance) inducer of numerous plant species. We provide a protocol for orchard-effective control of apple scab due to the ascomycete fungus Venturia inaequalis , by applying ASM in combination with a light integrated pest management program. Besides we pave the way for future optimization levers by demonstrating in controlled conditions (i) the high influence of apple genotypes, (ii) the ability of ASM to prime defenses in newly formed leaves, (iii) the positive effect of repeated elicitor applications, (iv) the additive effect of a thinning fruit agent.

  1. Corticosteroid-Induced MKP-1 Represses Pro-Inflammatory Cytokine Secretion by Enhancing Activity of Tristetraprolin (TTP) in ASM Cells.

    Science.gov (United States)

    Prabhala, Pavan; Bunge, Kristin; Ge, Qi; Ammit, Alaina J

    2016-10-01

    Exaggerated cytokine secretion drives pathogenesis of a number of chronic inflammatory diseases, including asthma. Anti-inflammatory pharmacotherapies, including corticosteroids, are front-line therapies and although they have proven clinical utility, the molecular mechanisms responsible for their actions are not fully understood. The corticosteroid-inducible gene, mitogen-activated protein kinase (MAPK) phosphatase 1 (MKP-1, DUSP1) has emerged as a key molecule responsible for the repressive effects of steroids. MKP-1 is known to deactivate p38 MAPK phosphorylation and can control the expression and activity of the mRNA destabilizing protein-tristetraprolin (TTP). But whether corticosteroid-induced MKP-1 acts via p38 MAPK-mediated modulation of TTP function in a pivotal airway cell type, airway smooth muscle (ASM), was unknown. While pretreatment of ASM cells with the corticosteroid dexamethasone (preventative protocol) is known to reduce ASM synthetic function in vitro, the impact of adding dexamethasone after stimulation (therapeutic protocol) had not been explored. Whether dexamethasone modulates TTP in a p38 MAPK-dependent manner in this cell type was also unknown. We address this herein and utilize an in vitro model of asthmatic inflammation where ASM cells were stimulated with the pro-asthmatic cytokine tumor necrosis factor (TNF) and the impact of adding dexamethasone 1 h after stimulation assessed. IL-6 mRNA expression and protein secretion was significantly repressed by dexamethasone acting in a temporally distinct manner to increase MKP-1, deactivate p38 MAPK, and modulate TTP phosphorylation status. In this way, dexamethasone-induced MKP-1 acts via p38 MAPK to switch on the mRNA destabilizing function of TTP to repress pro-inflammatory cytokine secretion from ASM cells. J. Cell. Physiol. 231: 2153-2158, 2016. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  2. SDZ ASM 981: an emerging safe and effective treatment for atopic dermatitis

    NARCIS (Netherlands)

    Luger, T.; van Leent, E. J.; Graeber, M.; Hedgecock, S.; Thurston, M.; Kandra, A.; Berth-Jones, J.; Bjerke, J.; Christophers, E.; Knop, J.; Knulst, A. C.; Morren, M.; Morris, A.; Reitamo, S.; Roed-Petersen, J.; Schoepf, E.; Thestrup-Pedersen, K.; van der Valk, P. G.; Bos, J. D.

    2001-01-01

    SDZ ASM 981 is a selective inhibitor of the production of pro-inflammatory cytokines from T cells and mast cells in vitro. It is the first ascomycin macrolactam derivative under development for the treatment of inflammatory skin diseases. This study was designed to determine the safety and efficacy

  3. Proceedings of the 5th Yugoslav Nuclear Society Conference (YUNSC-2004)

    International Nuclear Information System (INIS)

    Antic, D.

    2005-10-01

    The Fifth International Conference of the Yugoslav Nuclear Society (YUNSC-2004) was held in Belgrade from Monday, September 27, to Thursday, September 30, 2004. YUNSC-2004 is the fifth in the established series of conferences to be devoted to the promotion of scientific and technical co-operation of nuclear societies, especially of the countries in the Balkan region, and exchange of information and ideas between professionals in the nuclear field. One of the main goals, besides the good quality of the presented papers and the attendance of well-known experts, was the ambition of the Organising Committee to establish a traditional Yugoslav Nuclear Society conference that would gather nuclear experts from our country, Serbia and Montenegro experts currently working abroad and experts from neighboring and regional countries. The conference was organized by the Yugoslav Nuclear Society (YuNS) and coorganized by the VINCA Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro. As an introduction to the conference, the future project 'Vinca Institute Nuclear Decommissioning Program' was promoted by Dr. Milan Pesic, program manager. At the conference, out of 100 papers (55 papers by foreign authors) , 23 were presented in 9 Oral Sessions, while 77 contributions were presented in the Poster Session. The Fifth International Yugoslav Nuclear Society Conference 2004 (YUNSC 2004) are grouped into 13 chapters: Future of nuclear energy (5 papers), Numerical Methods in nuclear reactor analysis and design (6), Nuclear power plants and reactor safety (9), Fuel cycle and waste management (10), Research Reactors and Reactor Physics (8), ADS and Accelerators (1), Nuclear methods in science and technology (26), Radiation Protection (5), Depleted uranium (3), Nuclear medicine (4), Radiation Medicine (7), Environment (4). Proceedings were printed in 200 copies on CD October 2005. A separate abstract was prepared for each of these papers.

  4. Application of the French codes to the pressurized thermal shocks assessment

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Mingya; Wang, Rong Shan; Yu, Weiwei; Lu, Feng; Zhang, Guo Dong; Xue, Fei; Chen, Zhilin [Suzhou Nuclear Power Research Institute, Life Management Center, Suzhou (China); Qian, Guian [Paul Scherrer Institute, Nuclear Energy and Safety Department, Villigen (Switzerland); Shi, Jinhua [Amec Foster Wheeler, Clean Energy Department, Gloucester (United Kingdom)

    2016-12-15

    The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the 'screening criterion' for maximum allowable embrittlement of RPV material is developed based on the probabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, which are developed based on the deterministic fracture mechanics, there is no 'screening criterion'. In this paper, the methodology in the RCC-M and RSE-M codes, which are used for PTS analysis, are firstly discussed. The bases of the French codes are compared with ASME and FAVOR codes. A case study is also presented. The results show that the method in the RCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF) may be nonconservative. The SIF almost doubles if the weld residual stress is considered. The approaches included in the codes differ in many aspects, which may result in significant differences in the assessment results. Therefore, homogenization of the codes in the long time operation of nuclear power plants is needed.

  5. Application of the French Codes to the Pressurized Thermal Shocks Assessment

    Directory of Open Access Journals (Sweden)

    Mingya Chen

    2016-12-01

    Full Text Available The integrity of a reactor pressure vessel (RPV related to pressurized thermal shocks (PTSs has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the “screening criterion” for maximum allowable embrittlement of RPV material is developed based on the probabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, which are developed based on the deterministic fracture mechanics, there is no “screening criterion”. In this paper, the methodology in the RCC-M and RSE-M codes, which are used for PTS analysis, are firstly discussed. The bases of the French codes are compared with ASME and FAVOR codes. A case study is also presented. The results show that the method in the RCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF may be nonconservative. The SIF almost doubles if the weld residual stress is considered. The approaches included in the codes differ in many aspects, which may result in significant differences in the assessment results. Therefore, homogenization of the codes in the long time operation of nuclear power plants is needed.

  6. Application of the French codes to the pressurized thermal shocks assessment

    International Nuclear Information System (INIS)

    Chen, Mingya; Wang, Rong Shan; Yu, Weiwei; Lu, Feng; Zhang, Guo Dong; Xue, Fei; Chen, Zhilin; Qian, Guian; Shi, Jinhua

    2016-01-01

    The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the 'screening criterion' for maximum allowable embrittlement of RPV material is developed based on the probabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, which are developed based on the deterministic fracture mechanics, there is no 'screening criterion'. In this paper, the methodology in the RCC-M and RSE-M codes, which are used for PTS analysis, are firstly discussed. The bases of the French codes are compared with ASME and FAVOR codes. A case study is also presented. The results show that the method in the RCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF) may be nonconservative. The SIF almost doubles if the weld residual stress is considered. The approaches included in the codes differ in many aspects, which may result in significant differences in the assessment results. Therefore, homogenization of the codes in the long time operation of nuclear power plants is needed

  7. Advancing methods for reliably assessing motivational interviewing fidelity using the motivational interviewing skills code.

    Science.gov (United States)

    Lord, Sarah Peregrine; Can, Doğan; Yi, Michael; Marin, Rebeca; Dunn, Christopher W; Imel, Zac E; Georgiou, Panayiotis; Narayanan, Shrikanth; Steyvers, Mark; Atkins, David C

    2015-02-01

    The current paper presents novel methods for collecting MISC data and accurately assessing reliability of behavior codes at the level of the utterance. The MISC 2.1 was used to rate MI interviews from five randomized trials targeting alcohol and drug use. Sessions were coded at the utterance-level. Utterance-based coding reliability was estimated using three methods and compared to traditional reliability estimates of session tallies. Session-level reliability was generally higher compared to reliability using utterance-based codes, suggesting that typical methods for MISC reliability may be biased. These novel methods in MI fidelity data collection and reliability assessment provided rich data for therapist feedback and further analyses. Beyond implications for fidelity coding, utterance-level coding schemes may elucidate important elements in the counselor-client interaction that could inform theories of change and the practice of MI. Copyright © 2015 Elsevier Inc. All rights reserved.

  8. Parametric study of emerging high power accelerator applications using Accelerator Systems Model (ASM)

    International Nuclear Information System (INIS)

    Berwald, D.H.; Mendelsohn, S.S.; Myers, T.J.; Paulson, C.C.; Peacock, M.A.; Piaszczyk, CM.; Rathke, J.W.; Piechowiak, E.M.

    1996-01-01

    Emerging applications for high power rf linacs include fusion materials testing, generation of intense spallation neutrons for neutron physics and materials studies, production of nuclear materials and destruction of nuclear waste. Each requires the selection of an optimal configuration and operating parameters for its accelerator, rf power system and other supporting subsystems. Because of the high cost associated with these facilities, economic considerations become paramount, dictating a full evaluation of the electrical and rf performance, system reliability/availability, and capital, operating, and life cycle costs. The Accelerator Systems Model (ASM), expanded and modified by Northrop Grumman during 1993-96, provides a unique capability for detailed layout and evaluation of a wide variety of normal and superconducting accelerator and rf power configurations. This paper will discuss the current capabilities of ASM, including the available models and data base, and types of trade studies that can be performed for the above applications. (author)

  9. Scope and implementation of standards ASME N510 / N511 in air treatment system (HVAC) of the Asco nuclear power plant; Alcance e implementacion de las normas ASME N511 en el sistema de tratamiento de aire (HVAC) de la central nuclear de Asco

    Energy Technology Data Exchange (ETDEWEB)

    Jaimot Jimenez, J. J.

    2013-07-01

    With the ITC for renewal of license units 1 and 2 of Asco, the CSN It required the commissioning tests underway in the air, according to ASME N510 filter units. It is required that, for safety-related units, to undertake preventive inspections according to ASME N511. All these requirements, in tight deadlines, have represented a great challenge for the organizations of maintenance and engineering of ANAV.

  10. Closing session

    International Nuclear Information System (INIS)

    2014-01-01

    This part makes a summary of the different sessions and discussions of the workshop in a series of slide presentations: Summary of Opening Session; Summary of Session 1: Analysis of External Hazard Potential; Summary of session 2: Specific features of analysis and modeling of particular natural external hazards; Summary of session-3: Practices and research efforts on natural external events PSA; Summary of session 4: Modeling of NPP response to natural external events in PSA; Summary of session 5: Seismic Risk Analysis; Summary of session 6: Use of external events PSA with the focus on regulatory body role; Facilitated discussion 1 summary: Where do we stand in the analysis of external events?; Summary Facilitated Discussion 2: Findings and Good Practices for External Events Analysis

  11. Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

    International Nuclear Information System (INIS)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B.

    1995-11-01

    This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

  12. Proceedings of the 2004 annual petroleum days

    International Nuclear Information System (INIS)

    Millet, M.

    2004-01-01

    The 2004 annual petroleum days were organized by the AFTP, the CEPM and the GEP. The main theme, entitled 'hydrocarbons, energies of the future and environment' was dealing with the depletion of the petroleum resources and the necessity to reduce the greenhouse gases emissions (industrial facilities and transportation systems). The leaders of French companies (IFP, CGG, BP France, Total) explained their point of view during the plenary sessions, while during the parallel sessions, several experts presented the works in progress in the different branches of the petroleum industry. This article summarizes these different talks and treats of the following topics: the evolution of the global oil production and the abatement of air pollution, the evolution of exploration-production investments and the evolution of oil prices, the evaluation of reserves and their reevaluation, the global warming and the fight against the greenhouse effect (air pollution abatement, development of renewable energy sources, increase of energy efficiency, CO 2 sequestration etc..), evolution of transportation systems (hydrogen fuel cell, biomass fuels, hybrid electric-powered vehicles). A summary of the specialized sessions about new techniques concludes the article: improvements in stratigraphy, seismic surveys, and well logging. (J.S.)

  13. Proceedings of the European Symposium on Pressure Equipment - ESOPE 2007; Actes des Journees d'Etudes Europeennes Equipements sous Pression - ESOPE 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    orientations retained for pressure equipments used in the nuclear industry, the European standards and the international collaboration, the Chinese standards and finally the recent developments of the codes and standards of the ASME in the USA. ESOPE 2007 also includes a Poster Session organized in the context of the international exhibition, which allows the companies to present their industrial realizations in parallel to the Symposium. (author) [French] Tous les trois ans, et depuis maintenant trente ans, l AFIAP organise un symposium ou les experts et acteurs oeuvrant dans le domaine des equipements sous pression, qu'ils soient fixes ou transportables, peuvent se rencontrer et echanger sur tous les developpements touchant a leur activite. Ce qui etait dans un premier temps denomme 'Congres national sur la technologie des appareils a pression', puis 'Journees d'etude sur les appareils a pression', est devenu depuis 2001 les 'Journees d'etude Europeennes sur les equipements sous pression' ou encore 'European Symposium on Pressure Equipment' (ESOPE), marquant ainsi une volonte d'ouverture a l'Europe et a l'international dans un contexte marque par la mise en oeuvre des directives europeennes applicables a ces equipements. Les journees 2001 furent plus particulierement consacrees a la mise en oeuvre des directives harmonisant la construction des equipements, et les journees 2004 ont ete plus particulierement axees sur la gestion des equipements en service. Pour le symposium ESOPE 2007, le comite d organisation a souhaite reprendre ces deux themes sous les aspects de la securite et de la competitivite, ainsi que de l'innovation. La seance pleniere du dernier jour sera entierement consacree a ces themes et comportera une Table Ronde ou s'exprimeront des representants nationaux et europeens des pouvoirs publics, des representants des fabricants et utilisateurs, ainsi que des experts engages dans la

  14. Technical report on comparative analysis of ASME QA requirements and ISO series

    International Nuclear Information System (INIS)

    Kim, Kwan Hyun

    2000-06-01

    This technical report provides the differences on the QA requirement ASME and ISO in nuclear fields. This report applies to the quality assurance(QA) programmes of the design of two requirement. The organization having overall responsibility for the nuclear design, preservation, fabrication shall be described in this report in each stage of design project

  15. Development of an inelastic stress analysis code 'KINE-T' and its evaluations

    International Nuclear Information System (INIS)

    Kobatake, K.; Takahashi, S.; Suzuki, M.

    1977-01-01

    Referring to the ASME B and PVC Code Case 1592-7, the inelastic stress analysis is required for the designs of the class 1 components in elevated temperature if the results of the elastic stress analysis and/or simplified inelastic analysis do not satisfy the requirements. Authors programmed a two-dimensional axisymmetric inelastic analysis code 'KINE-T', and carried out its evaluations and an application. This FEM code is based on the incremental method and the following: elastic-plastic constitutive equation (yield condition of von Mises; flow rule of Prandtl-Reuss; Prager's hardening rule); creep constitutive equation (equation of state approach; flow rule of von Mises; strain hardening rule); the temperature dependency of the yield function is considered; solution procedure of the assembled stiffness matrix is the 'initial stress method'. After the completion of the programming, authors compared the output with not only theoretical results but also with those of the MARC code and the ANSYS code. In order to apply the code to the practical designing, authors settled a quasi-component two-dimensional axisymmetric model and a loading cycle (500 cycles). Then, an inelastic analysis and its integrity evaluation are carried out

  16. Frame Synchronization Without Attached Sync Markers

    Science.gov (United States)

    Hamkins, Jon

    2011-01-01

    We describe a method to synchronize codeword frames without making use of attached synchronization markers (ASMs). Instead, the synchronizer identifies the code structure present in the received symbols, by operating the decoder for a handful of iterations at each possible symbol offset and forming an appropriate metric. This method is computationally more complex and doesn't perform as well as frame synchronizers that utilize an ASM; nevertheless, the new synchronizer acquires frame synchronization in about two seconds when using a 600 kbps software decoder, and would take about 15 milliseconds on prototype hardware. It also eliminates the need for the ASMs, which is an attractive feature for short uplink codes whose coding gain would be diminished by the overheard of ASM bits. The lack of ASMs also would simplify clock distribution for the AR4JA low-density parity-check (LDPC) codes and adds a small amount to the coding gain as well (up to 0.2 dB).

  17. The status of Korean nuclear codes and standards

    International Nuclear Information System (INIS)

    Namha Kim; Jong-Hae Kim

    2005-01-01

    Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 200,0 and is expected to publish the 2005 edition. KEPIC was applied to the construction of Ulchin Nuclear Units 5 and 6 in 1997, and will be applicable to the construction of forthcoming nuclear power plants in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. The KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. The 2005 KEPIC edition will be retrofitted according to the ISO/IEC Guide 21- Adoption of International Standards as regional or national standards. KEA's efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. (authors)

  18. Precipitation-hardening stainless steel bars, shapes, and forgings (ASME SA-564 with additional requirements)

    International Nuclear Information System (INIS)

    1975-05-01

    A standard prescribing requirements for precipitation-hardening stainless steel bars, shapes, and forgings (ASME SA-564 with additional requirements) for nuclear and associated applications is presented. This standard supersedes RDT M 7-6T, dated January 1974. (U.S.)

  19. Exposure of a liquefied gas container to an external fire

    International Nuclear Information System (INIS)

    Raj, Phani K.

    2005-01-01

    In liquefied gas, bulk-storage facilities and plants, the separation distances between storage tanks and between a tank and a line of adjoining property that can be built are governed by local regulations and/or codes (e.g. National Fire Protection Association (NFPA) 58, 2004). Separation distance requirements have been in the NFPA 58 Code for over 60 years; however, no scientific foundations (either theoretical or experimental) are available for the specified distances. Even though the liquefied petroleum gas (LPG) industry has operated safely over the years, there is a question as to whether the code-specified distances provide sufficient safety to LPG-storage tanks, when they are exposed to large external fires. A radiation heat-transfer-based model is presented in this paper. The temporal variation of the vapor-wetted tank-wall temperature is calculated when exposed to thermal radiation from an external, non-impinging, large, 30.5 m (100 ft) diameter, highly radiative, hydrocarbon fuel (pool) fire located at a specified distance. Structural steel wall of a pressurized, liquefied gas container (such as the ASME LP-Gas tank) begins to lose its strength, when the wall temperature approaches a critical temperature, 810 K (1000 deg F). LP-Gas tank walls reaching close to this temperature will be a cause for major concern because of increased potential for tank failure, which could result in catastrophic consequences. Results from the model for exposure of different size ASME (LP-Gas) containers to a hydrocarbon pool fire of 30.5 m (100 ft) in diameter, located with its base edge at the separation distances specified by NFPA 58 [NFPA 58, Liquefied Petroleum Gas Code, Table 6.3.1, 2004 ed., National Fire Protection Association, Quincy, MA, 2004] indicate that the vapor-wetted wall temperature of the containers never reach the critical temperature under common wind conditions (0, 5 and 10 m/s), with the flame tilting towards the tank. This indicates that the separation

  20. Proceedings of the 2004 NASA/ONR Circulation Control Workshop, Part 2

    Science.gov (United States)

    Jones, Gregory S. (Editor); Joslin, Ronald D. (Editor)

    2005-01-01

    This conference proceeding is comprised of papers that were presented at the NASA/ONR Circulation Control Workshop held 16-17 March 2004 at the Radisson-Hampton in Hampton, VA. Over two full days, 30 papers and 4 posters were presented with 110 scientists and engineers in attendance, representing 3 countries. As technological advances influence the efficiency and effectiveness of aerodynamic and hydrodynamic applications, designs, and operations, this workshop was intended to address the technologies, systems, challenges and successes specific to Coanda driven circulation control in aerodynamics and hydrodynamics. A major goal of this workshop was to determine the state-of-the-art in circulation control and to assess the future directions and applications for circulation control. The 2004 workshop addressed applications, experiments, computations, and theories related to circulation control, emphasizing fundamental physics, systems analysis, and applied research. The workshop consisted of single session oral presentations, posters, and written papers that are documented in this unclassified conference proceeding. The format of this written proceeding follows the agenda of the workshop. Each paper is followed with the presentation given at the workshop. the editors compiled brief summaries for each effort that is at the end of this proceeding. These summaries include the paper, oral presentation, and questions or comments that occurred during the workshop. The 2004 Circulation Control Workshop focused on applications including Naval vehicles (Surface and Underwater vehicles), Fixed Wing Aviation (general aviation, commercial, cargo, and business aircraft); V/STOL platforms (helicopters, military aircraft, tilt rotors); propulsion systems (propellers, jet engines, gas turbines), and ground vehicles (automotive, trucks, and other); wind turbines, and other nontraditional applications (e.g., vacuum cleaner, ceiling fan). As part of the CFD focus area of the 2004 CC

  1. Ethical codes. Fig leaf argument, ballast or cultural element for radiation protection?; Ethik-Codes. Feigenblatt, Ballast oder Kulturelement fuer den Strahlenschutz?

    Energy Technology Data Exchange (ETDEWEB)

    Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

    2014-07-01

    The international association for radiation protection (IRPA) adopted in May 2004 a Code of Ethics in order to allow their members to hold an adequate professional level of ethical line of action. Based on this code of ethics the professional body of radiation protection (Fachverband fuer Strahlenschutz) has developed its own ethical code and adopted in 2005.

  2. IAEA to hold special session on nuclear terrorism

    International Nuclear Information System (INIS)

    2001-01-01

    Experts from around the world are meeting at the IAEA this week for an international symposium on nuclear safeguards, verification, and security. A special session on 2 November focuses on the issue of combating nuclear terrorism. The Special Session, which will bring together experts on nuclear terrorism from around the world, will deal with the following issues: The Psychology of terrorism; Intelligence, police and border protection; Guarding nuclear reactors and material from terrorists and thieves; The threat of nuclear terrorism: Nuclear weapons or other nuclear explosive devices; The threat of nuclear terrorism: Intentional dispersal of radioactive material - Sabotage of fixed installations or transport systems; The Legal Framework: Treaties and Conventions, Laws; Regulations and Codes of Practice; IAEA Nuclear Security and Safety Programmes

  3. Code of ethics: principles for ethical leadership.

    Science.gov (United States)

    Flite, Cathy A; Harman, Laurinda B

    2013-01-01

    The code of ethics for a professional association incorporates values, principles, and professional standards. A review and comparative analysis of a 1934 pledge and codes of ethics from 1957, 1977, 1988, 1998, 2004, and 2011 for a health information management association was conducted. Highlights of some changes in the healthcare delivery system are identified as a general context for the codes of ethics. The codes of ethics are examined in terms of professional values and changes in the language used to express the principles of the various codes.

  4. Emotion episodes during psychotherapy sessions among women newly diagnosed with gynecological cancers.

    Science.gov (United States)

    Myers Virtue, Shannon; Manne, Sharon L; Darabos, Kathleen; Heckman, Carolyn J; Ozga, Melissa; Kissane, David; Rubin, Stephen; Rosenblum, Norman

    2015-09-01

    The aim of this study was to describe emotion episodes during early and late psychotherapy sessions among women newly diagnosed with gynecological cancer and to examine whether the total number of emotion episodes during early and later sessions was associated with baseline psychological distress, dispositional emotion expressivity, and patient-rated therapeutic progress. The study utilized data from an ongoing study examining the efficacy of two psychotherapy interventions, a coping and communication intervention and a supportive counseling intervention, for women diagnosed with gynecological cancer. Emotion episode coding was completed for the first and sixth psychotherapy sessions for each patient randomized to receive psychotherapy (N = 173). Patients completed baseline survey measures of psychological distress and dispositional emotional expressivity and post-session ratings of therapeutic progress. The average number of emotion episodes was 7.4 in the first session and 5.2 episodes in the sixth session. In both sessions, the majority of emotion episodes contained only negative emotions and focused on a cancer-related topic. A higher number of emotion episodes in the first session was associated with higher psychological distress reported in the baseline survey (p = 0.02). A higher number of emotion episodes in the sixth session was associated with a higher number of emotion episodes in the first session (p psychotherapy among women diagnosed with gynecological cancer. Copyright © 2014 John Wiley & Sons, Ltd.

  5. Parallel Scaling Characteristics of Selected NERSC User ProjectCodes

    Energy Technology Data Exchange (ETDEWEB)

    Skinner, David; Verdier, Francesca; Anand, Harsh; Carter,Jonathan; Durst, Mark; Gerber, Richard

    2005-03-05

    This report documents parallel scaling characteristics of NERSC user project codes between Fiscal Year 2003 and the first half of Fiscal Year 2004 (Oct 2002-March 2004). The codes analyzed cover 60% of all the CPU hours delivered during that time frame on seaborg, a 6080 CPU IBM SP and the largest parallel computer at NERSC. The scale in terms of concurrency and problem size of the workload is analyzed. Drawing on batch queue logs, performance data and feedback from researchers we detail the motivations, benefits, and challenges of implementing highly parallel scientific codes on current NERSC High Performance Computing systems. An evaluation and outlook of the NERSC workload for Allocation Year 2005 is presented.

  6. The sensitivity analysis by adjoint method for the uncertainty evaluation of the CATHARE-2 code

    Energy Technology Data Exchange (ETDEWEB)

    Barre, F.; de Crecy, A.; Perret, C. [French Atomic Energy Commission (CEA), Grenoble (France)

    1995-09-01

    This paper presents the application of the DASM (Discrete Adjoint Sensitivity Method) to CATHARE 2 thermal-hydraulics code. In a first part, the basis of this method is presented. The mathematical model of the CATHARE 2 code is based on the two fluid six equation model. It is discretized using implicit time discretization and it is relatively easy to implement this method in the code. The DASM is the ASM directly applied to the algebraic system of the discretized code equations which has been demonstrated to be the only solution of the mathematical model. The ASM is an integral part of the new version 1.4 of CATHARE. It acts as a post-processing module. It has been qualified by comparison with the {open_quotes}brute force{close_quotes} technique. In a second part, an application of the DASM in CATHARE 2 is presented. It deals with the determination of the uncertainties of the constitutive relationships, which is a compulsory step for calculating the final uncertainty of a given response. First, the general principles of the method are explained: the constitutive relationship are represented by several parameters and the aim is to calculate the variance-covariance matrix of these parameters. The experimental results of the separate effect tests used to establish the correlation are considered. The variance of the corresponding results calculated by CATHARE are estimated by comparing experiment and calculation. A DASM calculation is carried out to provide the derivatives of the responses. The final covariance matrix is obtained by combination of the variance of the responses and those derivatives. Then, the application of this method to a simple case-the blowdown Canon experiment-is presented. This application has been successfully performed.

  7. The sensitivity analysis by adjoint method for the uncertainty evaluation of the CATHARE-2 code

    International Nuclear Information System (INIS)

    Barre, F.; de Crecy, A.; Perret, C.

    1995-01-01

    This paper presents the application of the DASM (Discrete Adjoint Sensitivity Method) to CATHARE 2 thermal-hydraulics code. In a first part, the basis of this method is presented. The mathematical model of the CATHARE 2 code is based on the two fluid six equation model. It is discretized using implicit time discretization and it is relatively easy to implement this method in the code. The DASM is the ASM directly applied to the algebraic system of the discretized code equations which has been demonstrated to be the only solution of the mathematical model. The ASM is an integral part of the new version 1.4 of CATHARE. It acts as a post-processing module. It has been qualified by comparison with the open-quotes brute forceclose quotes technique. In a second part, an application of the DASM in CATHARE 2 is presented. It deals with the determination of the uncertainties of the constitutive relationships, which is a compulsory step for calculating the final uncertainty of a given response. First, the general principles of the method are explained: the constitutive relationship are represented by several parameters and the aim is to calculate the variance-covariance matrix of these parameters. The experimental results of the separate effect tests used to establish the correlation are considered. The variance of the corresponding results calculated by CATHARE are estimated by comparing experiment and calculation. A DASM calculation is carried out to provide the derivatives of the responses. The final covariance matrix is obtained by combination of the variance of the responses and those derivatives. Then, the application of this method to a simple case-the blowdown Canon experiment-is presented. This application has been successfully performed

  8. Analysis and application of ratcheting evaluation procedure of Japanese high temperature design code DDS

    International Nuclear Information System (INIS)

    Lee, H. Y.; Kim, J. B.; Lee, J. H.

    2002-01-01

    In this study, the evaluation procedure of Japanese DDS code which was recently developed to assess the progressive inelastic deformation occurring under repetition of secondary stresses was analyzed and the evaluation results according to DDS was compared those of the thermal ratchet structural test carried out by KAERI to analyze the conservativeness of the code. The existing high temperature codes of US ASME-NH and French RCC-MR suggest the limited ratcheting procedures for only the load cases of cyclic secondary stresses under primary stresses. So they are improper to apply to the actual ratcheting problem which can occur under cyclic secondary membrane stresses due to the movement of hot free surface for the pool type LMR. DDS provides explicitly an analysis procedure of ratcheting due to moving thermal gradients near hot free surface. A comparison study was carried out between the results by the design code of DDS and by the structural test to investigate the conservativeness of DDS code, which showed that the evaluation results by DDS were in good agreement with those of the structural test

  9. The ASM-NSF Biology Scholars Program: An Evidence-Based Model for Faculty Development

    Directory of Open Access Journals (Sweden)

    Amy L. Chang

    2016-05-01

    Full Text Available The American Society for Microbiology (ASM established its ASM-NSF (National Science Foundation Biology Scholars Program (BSP to promote undergraduate education reform by 1 supporting biologists to implement evidence-based teaching practices, 2 engaging life science professional societies to facilitate biologists’ leadership in scholarly teaching within the discipline, and 3 participating in a teaching community that fosters disciplinary-level science, technology, engineering, and mathematics (STEM reform. Since 2005, the program has utilized year-long residency training to provide a continuum of learning and practice centered on principles from the scholarship of teaching and learning (SoTL to more than 270 participants (“scholars” from biology and multiple other disciplines. Additionally, the program has recruited 11 life science professional societies to support faculty development in SoTL and discipline-based education research (DBER. To identify the BSP’s long-term outcomes and impacts, ASM engaged an external evaluator to conduct a study of the program’s 2010­–2014 scholars (n = 127 and society partners. The study methods included online surveys, focus groups, participant observation, and analysis of various documents. Study participants indicate that the program achieved its proposed goals relative to scholarship, professional society impact, leadership, community, and faculty professional development. Although participants also identified barriers that hindered elements of their BSP participation, findings suggest that the program was essential to their development as faculty and provides evidence of the BSP as a model for other societies seeking to advance undergraduate science education reform. The BSP is the longest-standing faculty development program sponsored by a collective group of life science societies. This collaboration promotes success across a fragmented system of more than 80 societies representing the life

  10. The ASM-NSF Biology Scholars Program: An Evidence-Based Model for Faculty Development.

    Science.gov (United States)

    Chang, Amy L; Pribbenow, Christine M

    2016-05-01

    The American Society for Microbiology (ASM) established its ASM-NSF (National Science Foundation) Biology Scholars Program (BSP) to promote undergraduate education reform by 1) supporting biologists to implement evidence-based teaching practices, 2) engaging life science professional societies to facilitate biologists' leadership in scholarly teaching within the discipline, and 3) participating in a teaching community that fosters disciplinary-level science, technology, engineering, and mathematics (STEM) reform. Since 2005, the program has utilized year-long residency training to provide a continuum of learning and practice centered on principles from the scholarship of teaching and learning (SoTL) to more than 270 participants ("scholars") from biology and multiple other disciplines. Additionally, the program has recruited 11 life science professional societies to support faculty development in SoTL and discipline-based education research (DBER). To identify the BSP's long-term outcomes and impacts, ASM engaged an external evaluator to conduct a study of the program's 2010-2014 scholars (n = 127) and society partners. The study methods included online surveys, focus groups, participant observation, and analysis of various documents. Study participants indicate that the program achieved its proposed goals relative to scholarship, professional society impact, leadership, community, and faculty professional development. Although participants also identified barriers that hindered elements of their BSP participation, findings suggest that the program was essential to their development as faculty and provides evidence of the BSP as a model for other societies seeking to advance undergraduate science education reform. The BSP is the longest-standing faculty development program sponsored by a collective group of life science societies. This collaboration promotes success across a fragmented system of more than 80 societies representing the life sciences and helps

  11. Comparative studies on the effects of a yucca extract and acibenzolar-S-methyl (ASM) on inhibition of Venturia inaequalis in apple leaves

    DEFF Research Database (Denmark)

    Bengtsson, Marianne Vibeke; Wulff, Ednar Gadelha; Jørgensen, Hans Jørgen Lyngs

    2009-01-01

    The effect of an extract of Yucca schidigera on the control and infection process of the apple scab pathogen, Venturia inaequalis, was examined and compared with the chemical resistance inducer, acibenzolar-S-methyl (ASM). In seedling assays, both materials significantly reduced apple scab symptoms...... and pathogen sporulation on leaves and both showed similar control efficacies as the reference treatment, sulphur. Whereas yucca extract and sulphur gave significant inhibition of conidial germination in vitro, ASM did not inhibit germination. Histopathological studies of the infection process of V. inaequalis...... in apple leaves showed that the yucca extract primarily acted by inhibiting pre-penetration events and penetration itself. In contrast, the ASM treatment significantly inhibited more stages of the infection process (pre-penetration, penetration and post-penetration events). These observations suggest...

  12. Statistical theory applications and associated computer codes

    International Nuclear Information System (INIS)

    Prince, A.

    1980-01-01

    The general format is along the same lines as that used in the O.M. Session, i.e. an introduction to the nature of the physical problems and methods of solution based on the statistical model of the nucleus. Both binary and higher multiple reactions are considered. The computer codes used in this session are a combination of optical model and statistical theory. As with the O.M. sessions, the preparation of input and analysis of output are thoroughly examined. Again, comparison with experimental data serves to demonstrate the validity of the results and possible areas for improvement. (author)

  13. Nuclear class 1 piping stress analysis

    International Nuclear Information System (INIS)

    Lucas, J.C.R.; Maneschy, J.E.; Mariano, L.A.; Tamura, M.

    1981-01-01

    A nuclear class 1 piping stress analysis, according to the ASME code, is presented. The TRHEAT computer code has been used to determine the piping wall thermal gradient. The Nupipe computer code was employed for the piping stress analysis. Computer results were compared with the allowable criteria from the ASME code. (Author) [pt

  14. Alteraciones espirométricas en pacientes asmáticos del municipio Majibacoa, 2009-2013

    Directory of Open Access Journals (Sweden)

    Mailin Molina Leyva

    2014-08-01

    Full Text Available Se realizó un estudio descriptivo, con el objetivo de identificar alteraciones espirométricas en pacientes asmáticos del municipio Majibacoa, en el período comprendido desde enero del 2009 a enero del 2013. La muestra se integró por cincuenta pacientes asmáticos con más de 20 años de evolución de la enfermedad. Se les realizó previo consentimiento informado y una prueba espirométrica. Predominó el sexo femenino y las edades comprendidas entre 35 y 54 años. Prevalecieron los pacientes en la categoría de asma persistente severa. El volumen espiratorio forzado del primer segundo se comportó patológico en el mayor por ciento de los pacientes y la capacidad vital forzada mostró alteración en un menor número de pacientes. El patrón espirométrico obstructivo fue el más frecuente en los pacientes estudiados

  15. Improving coding accuracy in an academic practice.

    Science.gov (United States)

    Nguyen, Dana; O'Mara, Heather; Powell, Robert

    2017-01-01

    Practice management has become an increasingly important component of graduate medical education. This applies to every practice environment; private, academic, and military. One of the most critical aspects of practice management is documentation and coding for physician services, as they directly affect the financial success of any practice. Our quality improvement project aimed to implement a new and innovative method for teaching billing and coding in a longitudinal fashion in a family medicine residency. We hypothesized that implementation of a new teaching strategy would increase coding accuracy rates among residents and faculty. Design: single group, pretest-posttest. military family medicine residency clinic. Study populations: 7 faculty physicians and 18 resident physicians participated as learners in the project. Educational intervention: monthly structured coding learning sessions in the academic curriculum that involved learner-presented cases, small group case review, and large group discussion. overall coding accuracy (compliance) percentage and coding accuracy per year group for the subjects that were able to participate longitudinally. Statistical tests used: average coding accuracy for population; paired t test to assess improvement between 2 intervention periods, both aggregate and by year group. Overall coding accuracy rates remained stable over the course of time regardless of the modality of the educational intervention. A paired t test was conducted to compare coding accuracy rates at baseline (mean (M)=26.4%, SD=10%) to accuracy rates after all educational interventions were complete (M=26.8%, SD=12%); t24=-0.127, P=.90. Didactic teaching and small group discussion sessions did not improve overall coding accuracy in a residency practice. Future interventions could focus on educating providers at the individual level.

  16. Long periodicity of Blazar with RXTE ASM, TA and HEGRA

    OpenAIRE

    Osone, S.; Teshima, M.

    2002-01-01

    Long periodicity for Mkn501 during a large flare in 1997 have been reported by TA, HEGRA group. Here, we establish this periodicity with archival data of RXTE All Sky Monitor(ASM), Telescope Array(TA) and HEGRA with a chance probability less than $10^{-5}$. We also find that an origin of 23 day periodicity is related with a change of either a gamma factor of electrons $\\gamma$ or the magnetic field or a beaming factor. And, in order to search for a category which have a long periodicity, we m...

  17. Trends in asthma self-management skills and inhaled corticosteroid use during pregnancy and postpartum from 2004 to 2017.

    Science.gov (United States)

    Robijn, Annelies L; Jensen, Megan E; Gibson, Peter G; Powell, Heather; Giles, Warwick B; Clifton, Vicki L; Mattes, Joerg; Peek, Michael J; Barrett, Helen L; Seeho, Sean K; Callaway, Leonie K; Abbott, Alistair; Attia, John; Wark, Peter A; Murphy, Vanessa E

    2018-05-02

    Asthma exacerbations and medication non-adherence are significant clinical problems during pregnancy. While asthma self-management education is effective, the number of education sessions required to maximise asthma management knowledge and inhaler technique and whether improvements persist postpartum, are unknown. This paper describes how asthma knowledge, skills, and inhaled corticosteroid (ICS) use have changed over time. Data were obtained from 3 cohorts of pregnant women with asthma recruited in Newcastle, Australia between 2004 and 2017 (N = 895). Medication use, adherence, knowledge, and inhaler technique were compared between cohorts. Changes in self-management knowledge/skills and women's perception of medication risk to the fetus were assessed in 685 women with 5 assessments during pregnancy, and 95 women who had a postpartum assessment. At study entry, 41%, 29%, and 38% of participants used ICS in the 2004, 2007, and 2013 cohorts, respectively (p = 0.017), with 40% non-adherence in each cohort. Self-management skills of pregnant women with asthma did not improve between 2004 and 2017 and possession of a written action plan remained low. Maximum improvements were reached by 3 sessions for medications knowledge and one session for inhaler technique, and were maintained postpartum. ICS adherence was maximally improved after one session, but not maintained postpartum. Perceived risk of asthma medications on the fetus was highest for corticosteroid-containing medication; and was significantly reduced following education. There was a high prevalence of non-adherence and poor self-management skills in all cohorts. More awareness of the importance of optimal asthma management during pregnancy is warranted, since no improvements were observed over the past decade.

  18. Doxofylline does not increase formoterol-induced cAMP nor MKP-1 expression in ASM cells resulting in lack of anti-inflammatory effect.

    Science.gov (United States)

    Patel, Brijeshkumar S; Kugel, Michael J; Baehring, Gina; Ammit, Alaina J

    2017-08-01

    The xanthine doxofylline has been examined in clinical trials and shown to have efficacy and greater tolerability than theophylline in asthma and chronic obstructive pulmonary disease. The 'novofylline' doxofylline has demonstrated bronchodilatory and anti-inflammatory actions in in vivo and ex vivo experimental models of respiratory disease. However, there are limited studies in vitro. We address this herein and examine whether doxofylline has anti-inflammatory impact on primary cultures of airway smooth muscle (ASM) cells. We conduct a series of investigations comparing and contrasting doxofylline with the archetypal xanthine, theophylline, and the specific phosphodiesterase (PDE) 4 inhibitor, cilomilast. We confirm that the xanthine drugs do not have action as PDE inhibitors in ASM cells. Unlike cilomilast, doxofylline (and theophylline) do not increase cAMP production in ASM cells induced by long-acting β 2 -agonist formoterol. Similar to theophylline, and consistent with the lack of cAMP potentiation, doxofylline does not augment formoterol-induced upregulation of the anti-inflammatory protein mitogen-activated protein kinase phosphatase 1 (MKP-1). However, when we examine the effect of doxofylline on secretion of the interleukin 8 from ASM cells stimulated by tumour necrosis factor (an in vitro surrogate measure of inflammation), there was no repression of inflammation. This is in contrast to the anti-inflammatory impact exerted by theophylline and cilomilast in confirmatory experiments. In summary, our study is the first to examine the effect of doxofylline on ASM cells in vitro and highlights some distinct differences between two key members of xanthine drug family, doxofylline and theophylline. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Recommendations for codes and standards to be used for design and fabrication of high level waste canister

    International Nuclear Information System (INIS)

    Bermingham, A.J.; Booker, R.J.; Booth, H.R.; Ruehle, W.G.; Shevekov, S.; Silvester, A.G.; Tagart, S.W.; Thomas, J.A.; West, R.G.

    1978-01-01

    This study identifies codes, standards, and regulatory requirements for developing design criteria for high-level waste (HLW) canisters for commercial operation. It has been determined that the canister should be designed as a pressure vessel without provision for any overpressure protection type devices. It is recommended that the HLW canister be designed and fabricated to the requirements of the ASME Section III Code, Division 1 rules, for Code Class 3 components. Identification of other applicable industry and regulatory guides and standards are provided in this report. Requirements for the Design Specification are found in the ASME Section III Code. It is recommended that design verification be conducted principally with prototype testing which will encompass normal and accident service conditions during all phases of the canister life. Adequacy of existing quality assurance and licensing standards for the canister was investigated. One of the recommendations derived from this study is a requirement that the canister be N stamped. In addition, acceptance standards for the HLW waste should be established and the waste qualified to those standards before the canister is sealed. A preliminary investigation of use of an overpack for the canister has been made, and it is concluded that the use of an overpack, as an integral part of overall canister design, is undesirable, both from a design and economics standpoint. However, use of shipping cask liners and overpack type containers at the Federal repository may make the canister and HLW management safer and more cost effective. There are several possible concepts for canister closure design. These concepts can be adapted to the canister with or without an overpack. A remote seal weld closure is considered to be one of the most suitable closure methods; however, mechanical seals should also be investigated

  20. Pressure Safety Program Implementation at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply

  1. Session-RPE for quantifying the load of different youth basketball training sessions.

    Science.gov (United States)

    Lupo, C; Tessitore, A; Gasperi, L; Gomez, Mar

    2017-03-01

    The aim of the study was to evaluate youth basketball training, verifying the reliability of the session-RPE method in relation to session duration (session) categories. Six male youth basketball players (age, 16.5±0.5 years; height, 195.5±6.75 cm; body mass, 93.9±10.9 kg; and body mass index, 23.6±2.8 kg.m -2 ) were monitored (HR, type and duration of workouts) during 15 (66 individual) training sessions (80±26 minutes). Edwards' HR method was used as a reference measure of internal training load (ITL); the CR-10 RPE scale was administered 30 minutes after the end of each session. The results obtained showed that all comparisons between different session durations and workout portions revealed effects in term of Edwards' ITLs except for warm-up portions. Moderate to strong relationships between Edwards' and session- RPE methods emerged for all sessions (r = .85, P sessions (r range = .79 - .95, P session durations (session-RPE to monitor the ITL, regardless of session durations and workout portions.

  2. Statistical re-evaluation of the ASME K{sub IC} and K{sub IR} fracture toughness reference curves

    Energy Technology Data Exchange (ETDEWEB)

    Wallin, K.; Rintamaa, R. [Valtion Teknillinen Tutkimuskeskus, Espoo (Finland)

    1998-11-01

    Historically the ASME reference curves have been treated as representing absolute deterministic lower bound curves of fracture toughness. In reality, this is not the case. They represent only deterministic lower bound curves to a specific set of data, which represent a certain probability range. A recently developed statistical lower bound estimation method called the `Master curve`, has been proposed as a candidate for a new lower bound reference curve concept. From a regulatory point of view, the Master curve is somewhat problematic in that it does not claim to be an absolute deterministic lower bound, but corresponds to a specific theoretical failure probability that can be chosen freely based on application. In order to be able to substitute the old ASME reference curves with lower bound curves based on the master curve concept, the inherent statistical nature (and confidence level) of the ASME reference curves must be revealed. In order to estimate the true inherent level of safety, represented by the reference curves, the original data base was re-evaluated with statistical methods and compared to an analysis based on the master curve concept. The analysis reveals that the 5% lower bound Master curve has the same inherent degree of safety as originally intended for the K{sub IC}-reference curve. Similarly, the 1% lower bound Master curve corresponds to the K{sub IR}-reference curve. (orig.)

  3. TRAIL death receptor 4 signaling via lysosome fusion and membrane raft clustering in coronary arterial endothelial cells: evidence from ASM knockout mice.

    Science.gov (United States)

    Li, Xiang; Han, Wei-Qing; Boini, Krishna M; Xia, Min; Zhang, Yang; Li, Pin-Lan

    2013-01-01

    Tumor necrosis factor-related apoptosis-inducing ligand (TRAIL) and its receptor, death receptor 4 (DR4), have been implicated in the development of endothelial dysfunction and atherosclerosis. However, the signaling mechanism mediating DR4 activation leading to endothelial injury remains unclear. We recently demonstrated that ceramide production via hydrolysis of membrane sphingomyelin by acid sphingomyelinase (ASM) results in membrane raft (MR) clustering and the formation of important redox signaling platforms, which play a crucial role in amplifying redox signaling in endothelial cells leading to endothelial dysfunction. The present study aims to investigate whether TRAIL triggers MR clustering via lysosome fusion and ASM activation, thereby conducting transmembrane redox signaling and changing endothelial function. Using confocal microscopy, we found that TRAIL induced MR clustering and co-localized with DR4 in coronary arterial endothelial cells (CAECs) isolated from wild-type (Smpd1 (+/+)) mice. Furthermore, TRAIL triggered ASM translocation, ceramide production, and NADPH oxidase aggregation in MR clusters in Smpd1 ( +/+ ) CAECs, whereas these observations were not found in Smpd1 (-/-) CAECs. Moreover, ASM deficiency reduced TRAIL-induced O(2) (-[Symbol: see text]) production in CAECs and abolished TRAIL-induced impairment on endothelium-dependent vasodilation in small resistance arteries. By measuring fluorescence resonance energy transfer, we found that Lamp-1 (lysosome membrane marker protein) and ganglioside G(M1) (MR marker) were trafficking together in Smpd1 (+/+) CAECs, which was absent in Smpd1 (-/-) CAECs. Consistently, fluorescence imaging of living cells with specific lysosome probes demonstrated that TRAIL-induced lysosome fusion with membrane was also absent in Smpd1 (-/-) CAECs. Taken together, these results suggest that ASM is essential for TRAIL-induced lysosomal trafficking, membrane fusion and formation of MR redox signaling platforms

  4. Towards a consensus-based biokinetic model for green microalgae - The ASM-A.

    Science.gov (United States)

    Wágner, Dorottya S; Valverde-Pérez, Borja; Sæbø, Mariann; Bregua de la Sotilla, Marta; Van Wagenen, Jonathan; Smets, Barth F; Plósz, Benedek Gy

    2016-10-15

    Cultivation of microalgae in open ponds and closed photobioreactors (PBRs) using wastewater resources offers an opportunity for biochemical nutrient recovery. Effective reactor system design and process control of PBRs requires process models. Several models with different complexities have been developed to predict microalgal growth. However, none of these models can effectively describe all the relevant processes when microalgal growth is coupled with nutrient removal and recovery from wastewaters. Here, we present a mathematical model developed to simulate green microalgal growth (ASM-A) using the systematic approach of the activated sludge modelling (ASM) framework. The process model - identified based on a literature review and using new experimental data - accounts for factors influencing photoautotrophic and heterotrophic microalgal growth, nutrient uptake and storage (i.e. Droop model) and decay of microalgae. Model parameters were estimated using laboratory-scale batch and sequenced batch experiments using the novel Latin Hypercube Sampling based Simplex (LHSS) method. The model was evaluated using independent data obtained in a 24-L PBR operated in sequenced batch mode. Identifiability of the model was assessed. The model can effectively describe microalgal biomass growth, ammonia and phosphate concentrations as well as the phosphorus storage using a set of average parameter values estimated with the experimental data. A statistical analysis of simulation and measured data suggests that culture history and substrate availability can introduce significant variability on parameter values for predicting the reaction rates for bulk nitrate and the intracellularly stored nitrogen state-variables, thereby requiring scenario specific model calibration. ASM-A was identified using standard cultivation medium and it can provide a platform for extensions accounting for factors influencing algal growth and nutrient storage using wastewater resources. Copyright

  5. Civil Behavior, Safe-School Planning, and Dress Codes

    Science.gov (United States)

    Studak, Cathryn M.; Workman, Jane E.

    2007-01-01

    This research examined news reports in order to identify incidents that precipitated dress code revisions. News reports were examined within the framework of rules for civil behavior. Using key words "school dress codes" and "violence," LEXIS/NEXIS was used to access 104 articles from 44 U.S. newspapers from December 3, 2004 to December 2, 2005.…

  6. Efecto de budesonida sobre la densidad y el metabolismo óseo en niños asmáticos

    Directory of Open Access Journals (Sweden)

    Paoli de Valeri Mariela

    2000-01-01

    Full Text Available OBJETIVO: Determinar el efecto de la administración de budesonida inhalado sobre la densidad, el contenido mineral y el metabolismo óseo en niños asmáticos. MATERIAL Y MÉTODOS: Estudio transversal realizado de septiembre de 1996 a julio de 1997, en el que se estudiaron 38 niños y niñas de entre 6 y 11 años de edad, seleccionados de la consulta externa de neumonología infantil del Instituto Autónomo Hospital Universitario de Los Andes, Mérida, Venezuela. Se constituyeron tres grupos: nueve niños asmáticos tratados con budesonida inhalado (300 µg/día en promedio durante más de seis meses, (grupo A, 14 niños asmáticos que no recibieron tratamiento esteroideo (grupo B y 15 niños no asmáticos (grupo C. A todos se les practicó una evaluación ósea con marcadores de formación y resorción y con una medición de la densidad (DMO y el contenido mineral óseo (CMO. Se calcularon medidas de tendencia central y de dispersión, se realizó análisis de varianza, y se utilizaron las pruebas de Fisher y Scheffé para comparación de medias. RESULTADOS: En los grupos estudiados (A, B y C los niveles séricos de calcio fueron 9.1±0.3; 9.6±0.4; 9.3±0.6 mg/ml; los de osteocalcina fueron 14.8±4.6; 13.0±2.5; 11.9±3.4 ng/dl; los de telopéptido carboxiterminal del colágeno tipo I (ICTP fueron 19.6±16.5; 14.2±15.4; 13.0±18.3 µg/l; la DMO fue de 0.67±0.06; 0.68±0.06; 0.69±0.06 g/cm², y el CMO fue de 1 158.8±217.4; 1 106.4±256.1; 1 176.5±240.5 g, respectivamente. No hubo diferencias significativas entre los grupos. CONCLUSIONES: La administración de budesonida inhalada en dosis de 100 a 400 µg/día por un periodo de seis meses no produce modificaciones en la densidad y en el metabolismo óseo en niños asmáticos.

  7. Comportamiento de variables clínico-epidemiológicas en pacientes asmáticos. Consultorio Médico de Familia 14, Puerto Padre

    Directory of Open Access Journals (Sweden)

    José Ramón Martínez Pérez

    2015-12-01

    Full Text Available Se realizó un estudio descriptivo de corte transversal en 40 pacientes asmáticos de todas las edades, pertenecientes al Consultorio 14 del área de salud de Puerto Padre, provincia de Las Tunas, durante los meses de enero a junio de 2008; con el objetivo de determinar el comportamiento de variables clínico-epidemiológicas en dichos pacientes. Para cumplimentar los objetivos se diseñó una encuesta que recogió las variables de interés. El análisis se hizo a través del sistema Statistix, permitiendo  obtener  la distribución de frecuencia y los porcientos. El test de Chi-Cuadrado se empleó en la comparación de variables cualitativas. Los resultados fueron descritos, interpretados y comparados con otros estudios. Se concluye que los pacientes grado I según Kraeppelin son los mas representados en nuestra población de pacientes asmáticos;  los broncodilatadores son los medicamentos mas utilizados por la población asmática estudiada; el incumplimiento del tratamiento medicamentoso no se relacionó con la severidad de la enfermedad en la población estudiada;  las malas condiciones de la vivienda y  el tabaquismo influyeron de forma negativa en la evolución del paciente asmático.

  8. Structural integrity assessment of a pressure container component. Design and service code implementation. Case studies

    International Nuclear Information System (INIS)

    Sanzi, H.C.

    2006-01-01

    In the present work, the most important results of the local stresses occurred in the cracked pipes with a axial through-wall crack (outer), produced during operation of a Petrochemical Plant, using finite elements method, are presented. As requested, the component has been verified based 3D FE plastic analysis, under the postulated failure loading, assuring with this method a high degree of accuracy in the results. Codes used by Design and Service, as ASME Section VIII Div. 2 and API 579, have been used in the analysis. (author) [es

  9. Standardized Observational Assessment of Attention Deficit Hyperactivity Disorder Combined and Predominantly Inattentive Subtypes. I. Test Session Observations

    Science.gov (United States)

    McConaughy, Stephanie H.; Ivanova, Masha Y.; Antshel, Kevin; Eiraldi, Ricardo B.

    2009-01-01

    Test examiners used the Test Observation Form (McConaughy & Achenbach, 2004) to rate test session behavior of 177 6- to 11-year-old children during administration of the Wechsler Intelligence Scale for Children-Fourth Edition (WISC-IV) and Wechsler Individual Achievement Tests-Second Edition (WIAT-II). Participants were assigned to four groups…

  10. Proceedings of the Areva Technical Days. Session 5

    International Nuclear Information System (INIS)

    2004-01-01

    This document presents the proceedings of the Areva technical days, presented during the session 5 the 9 and 10 december 2004, at Istanbul. It deals with the operations of the transmission and distribution division. With manufacturing facilities in over 40 countries and a sales network in over 100, Areva offers customers technological solutions for nuclear power generation and electricity transmission and distribution (the Group also provides interconnect systems to the telecommunications, computer and automotive markets). It provides five topics: a general presentation of Areva, the strategic stakes for transmission and distribution by world-zone, economic and strategic stakes of business unit products, business unit systems and business unit automation. (A.L.B.)

  11. Proceedings of the Areva Technical Days. Session 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document presents the proceedings of the Areva technical days, presented during the session 5 the 9 and 10 december 2004, at Istanbul. It deals with the operations of the transmission and distribution division. With manufacturing facilities in over 40 countries and a sales network in over 100, Areva offers customers technological solutions for nuclear power generation and electricity transmission and distribution (the Group also provides interconnect systems to the telecommunications, computer and automotive markets). It provides five topics: a general presentation of Areva, the strategic stakes for transmission and distribution by world-zone, economic and strategic stakes of business unit products, business unit systems and business unit automation. (A.L.B.)

  12. Network Coding in the Bidirectional Cross

    DEFF Research Database (Denmark)

    Ertli, Gergö; Paramanathan, Achuthan; Rein, Stephan Alexander

    2013-01-01

    This paper presents a detailed performance evaluation of inter-session network coding in wireless meshed networks in terms of throughput and energy consumption. A full analytical model is given for three different communication approaches for the bidirectional cross topology using an IEEE 802.11 ...

  13. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/ where you can find the detailed course contents under the "Microsoft Office XP" catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participa...

  14. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office XP' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the app...

  15. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the "Microsoft Office XP" catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the partici...

  16. CERN Technical Training 2004 - Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office XP' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the ap...

  17. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office XP' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the ...

  18. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A 'blended learning' course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on November 9, morning. Course sessions are self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the appropriate WBT...

  19. Post-Session Authentication

    DEFF Research Database (Denmark)

    Ahmed, Naveed; Jensen, Christian D.

    2012-01-01

    Entity authentication provides confidence in the claimed identity of a peer entity, but the manner in which this goal is achieved results in different types of authentication. An important factor in this regard is the order between authentication and the execution of the associated session....... In this paper, we consider the case of post-session authentication, where parties authenticate each other at the end of their interactive session. This use of authentication is different from session-less authentication (e.g., in RFID) and pre-session authentication (e.g., for access control.) Post......-session authentication, although a new term, is not a new concept; it is the basis of at least a few practical schemes. We, for the first time, systematically study it and present the underlying authentication model. Further, we show that an important class of problems is solvable using post-session authentication...

  20. 2004 Annual report

    International Nuclear Information System (INIS)

    2005-01-01

    This annual report presents information of the main activities on the scope of radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2004. The main topics are the regulatory framework, the national systems to supervise nuclear installations, the emergency systems, the environmental control, the laboratories of the ARN, the institutional relations and the non-proliferation, the training and the public information, the radiological and the nuclear safety inspections, the safeguards and the physical protection, the quality assurance in the ARN, the environmental monitoring, and the human and economic resources. Also, this publication has four annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; ethical code; measurements and evaluations of the drinking water in Ezeiza (Argentina)

  1. Effect of patients' rights training sessions for nurses on perceptions of nurses and patients.

    Science.gov (United States)

    Ibrahim, Sanaa A; Hassan, Mona A; Hamouda, Seham Ibrahim; Abd Allah, Nama M

    2017-11-01

    Patients' rights are universal values that must be respected; however, it is not easy to put such values and principles into effect as approaches and attitudes differ from individual to individual, from society to society, and from country to country. If we want to reach a general conclusion about the status of patient rights in the world as whole, we should examine the situation in individual countries. To study the effect of training sessions for nurses about patients' rights on the perceptions of nurses and patients in two Egyptian hospitals. Quasi-experimental with pre- and posttest design was used in this study. Two groups of participants were included in the study: the first with 97 nurses and the second with 135 patients. A questionnaire sheet was used for nurses and patients to assess their perceptions about patients' rights before starting sessions. The training sessions were developed based on the baseline information gathered in the assessment phase and related literature. After the implementation of the sessions, a posttest was immediately conducted for nurses, while for patients the posttest was conducted 1 month after implementation to evaluate the effect of the nurses' training sessions on the patients' perceptions. The same tools were used in pretest and posttest. Ethical considerations: Written approval was sought and obtained from the administrators of the studied hospitals prior to conducting the study. Oral consent was obtained from nurses and patients willing to participate. Confidentiality and anonymity of the participants were strictly maintained through code numbers on the questionnaires. The improvement in nurses' knowledge and perceptions about patients' rights after implementation of the training sessions was remarkable. Moreover, an improvement in patients' perceptions regarding their rights was reported. Repetition of the training sessions is suggested to achieve continuous improvement. Provision of posters and booklets about a bill of

  2. Fast convolutional sparse coding using matrix inversion lemma

    Czech Academy of Sciences Publication Activity Database

    Šorel, Michal; Šroubek, Filip

    2016-01-01

    Roč. 55, č. 1 (2016), s. 44-51 ISSN 1051-2004 R&D Projects: GA ČR GA13-29225S Institutional support: RVO:67985556 Keywords : Convolutional sparse coding * Feature learning * Deconvolution networks * Shift-invariant sparse coding Subject RIV: JD - Computer Applications, Robotics Impact factor: 2.337, year: 2016 http://library.utia.cas.cz/separaty/2016/ZOI/sorel-0459332.pdf

  3. 98th LHCC meeting Agenda OPEN Session and CLOSED Session

    CERN Document Server

    CERN. Geneva

    2009-01-01

    OPEN Session on Wednesday, 8 July at 9h00-11h00 in Main Auditorium, Live webcast, followed by CLOSED Session, Conference room 160-1-009 11h20-17h00. CLOSED Session continued on Thursday, 9 July at 9h00-12h30

  4. Activated sludge model (ASM) based modelling of membrane bioreactor (MBR) processes: a critical review with special regard to MBR specificities.

    Science.gov (United States)

    Fenu, A; Guglielmi, G; Jimenez, J; Spèrandio, M; Saroj, D; Lesjean, B; Brepols, C; Thoeye, C; Nopens, I

    2010-08-01

    Membrane bioreactors (MBRs) have been increasingly employed for municipal and industrial wastewater treatment in the last decade. The efforts for modelling of such wastewater treatment systems have always targeted either the biological processes (treatment quality target) as well as the various aspects of engineering (cost effective design and operation). The development of Activated Sludge Models (ASM) was an important evolution in the modelling of Conventional Activated Sludge (CAS) processes and their use is now very well established. However, although they were initially developed to describe CAS processes, they have simply been transferred and applied to MBR processes. Recent studies on MBR biological processes have reported several crucial specificities: medium to very high sludge retention times, high mixed liquor concentration, accumulation of soluble microbial products (SMP) rejected by the membrane filtration step, and high aeration rates for scouring purposes. These aspects raise the question as to what extent the ASM framework is applicable to MBR processes. Several studies highlighting some of the aforementioned issues are scattered through the literature. Hence, through a concise and structured overview of the past developments and current state-of-the-art in biological modelling of MBR, this review explores ASM-based modelling applied to MBR processes. The work aims to synthesize previous studies and differentiates between unmodified and modified applications of ASM to MBR. Particular emphasis is placed on influent fractionation, biokinetics, and soluble microbial products (SMPs)/exo-polymeric substances (EPS) modelling, and suggestions are put forward as to good modelling practice with regard to MBR modelling both for end-users and academia. A last section highlights shortcomings and future needs for improved biological modelling of MBR processes. (c) 2010 Elsevier Ltd. All rights reserved.

  5. Annual report for 2004

    International Nuclear Information System (INIS)

    2005-01-01

    Article VI.J of the IAEA's Statute requires the Board of Governors to submit 'an annual report to the General Conference concerning the affairs of the Agency and any projects approved by the Agency'. This report covers the period 1 January to 31 December 2004. The Annual Report reviews the results of the Agency's programme according to the three pillars of technology, safety and verification. The main part of the report generally follows the programme structure as it applied in 2004. The introductory chapter, 'The Agency and the World in 2004', seeks to provide a thematic analysis, based on the three pillars, of the Agency's activities within the overall context of notable developments during the year. Information on specific issues can be found in the latest editions of the Agency's Nuclear Safety Review, Nuclear Technology Review and Technical Cooperation Report. For the convenience of readers, these documents are available on the CD-ROM attached to this report. Additional information covering various aspects of the Agency's programme is also provided on the attached CD-ROM, and is also available on the Agency's iaea.org web site (http://www.iaea.org/Worldatom/Documents/Anrep/Anrep2004/). The Board of Governors oversees the ongoing operations of the Agency. It comprises 35 Member States and generally meets five times a year or more frequently if required for specific situations. Among its functions, the Board adopts the Agency's programme for the incoming biennium and makes recommendations on the Agency's budget to the General Conference. In 2004, the Board considered the Nuclear Technology Review 2004 and various activities related to nuclear science, technology and applications. This included authorizing the implementation of the Programme of Action for Cancer Therapy (PACT). In the area of safety and security, it considered the Nuclear Safety Review for the Year 2003 and related activities. It approved four Action Plans on various safety related activities and

  6. Annual report for 2004

    International Nuclear Information System (INIS)

    2005-01-01

    Article VI.J of the IAEA's Statute requires the Board of Governors to submit 'an annual report to the General Conference concerning the aff airs of the Agency and any projects approved by the Agency'. This report covers the period 1 January to 31 December 2004. The Annual Report reviews the results of the Agency's programme according to the three pillars of technology, safety and verification. The main part of the report generally follows the programme structure as it applied in 2004. The introductory chapter, 'The Agency and the World in 2004', seeks to provide a thematic analysis, based on the three pillars, of the Agency's activities within the overall context of notable developments during the year. Information on specific issues can be found in the latest editions of the Agency's Nuclear Safety Review, Nuclear Technology Review and Technical Cooperation Report. For the convenience of readers, these documents are available on the CD-ROM attached to this report. Additional information covering various aspects of the Agency's programme is also provided on the attached CD-ROM, and is also available on the Agency's iaea.org web site (http://www.iaea.org/Worldatom/Documents/Anrep/Anrep2004/). The Board of Governors oversees the ongoing operations of the Agency. It comprises 35 Member States and generally meets five times a year or more frequently if required for specific situations. Among its functions, the Board adopts the Agency's programme for the incoming biennium and makes recommendations on the Agency's budget to the General Conference. In 2004, the Board considered the Nuclear Technology Review 2004 and various activities related to nuclear science, technology and applications. This included authorizing the implementation of the Programme of Action for Cancer Therapy (PACT). In the area of safety and security, it considered the Nuclear Safety Review for the Year 2003 and related activities. It approved four Action Plans on various safety related activities

  7. Modifications to LLNL Plutonium Packaging Systems (PuPS) to achieve ASME VIII UW-13.2(d) Requirements for the DOE Standard 3013-00 Outer Can Weld

    International Nuclear Information System (INIS)

    Riley, D; Dodson, K

    2001-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Packaging System (PuPS) prepares packages to meet the DOE Standard 3013 (Reference 1). The PuPS equipment was supplied by the British Nuclear Fuels Limited (BNFL). The DOE Standard 3013 requires that the welding of the Outer Can meets ASME Section VIII Division 1 (Reference 2). ASME Section VIII references to ASME Section IX (Reference 3) for most of the welding requirements, but UW-13.2 (d) of Section VIII requires a certain depth and width of the weld. In this document the UW-13.2(d) requirement is described as the (a+b)/2t s ratio. This ratio has to be greater than or equal to one to meet the requirements of UW-13.2(d). The Outer Can welds had not been meeting this requirement. Three methods are being followed to resolve this issue: (1) Modify the welding parameters to achieve the requirement, (2) Submit a weld case to ASME that changes the UW-13.2(d) requirement for their review and approval, and (3) Change the requirements in the DOE-STD-3013. Each of these methods are being pursued. This report addresses how the first method was addressed for the LLNL PuPS. The experimental work involved adjusting the Outer Can rotational speed and the power applied to the can. These adjustments resulted in being able to achieve the ASME VIII, UW-13.2(d) requirement

  8. Session-RPE for quantifying the load of different youth basketball training sessions

    Directory of Open Access Journals (Sweden)

    C Lupo

    2016-12-01

    Full Text Available The aim of the study was to evaluate youth basketball training, verifying the reliability of the session-RPE method in relation to session duration (< and ≥ 80 minutes and workout typology (reduced and high warm-up, conditioning, technical, tactical, game portions within a single session categories. Six male youth basketball players (age, 16.5±0.5 years; height, 195.5±6.75 cm; body mass, 93.9±10.9 kg; and body mass index, 23.6±2.8 kg.m-2 were monitored (HR, type and duration of workouts during 15 (66 individual training sessions (80±26 minutes. Edwards’ HR method was used as a reference measure of internal training load (ITL; the CR-10 RPE scale was administered 30 minutes after the end of each session. The results obtained showed that all comparisons between different session durations and workout portions revealed effects in term of Edwards’ ITLs except for warm-up portions. Moderate to strong relationships between Edwards’ and session- RPE methods emerged for all sessions (r = .85, P < .001, player’s sessions (r range = .79 - .95, P < .001, session durations (< 80 minutes: r = .67, P < .001; ≥ 80 minutes: r = .75, P < .001, and workout portions (r range = .78 - .89, P range = .002 - < .001. The findings indicated that coaches of youth basketball players can successfully use session-RPE to monitor the ITL, regardless of session durations and workout portions.

  9. Code-switching and communicative competence in the language ...

    African Journals Online (AJOL)

    Code-switching and communicative competence in the language classroom. ... that both teachers and learners engage in CS behaviour in classroom interaction. The paper examines language teaching sessions of Grade 8 and 9 learners in ...

  10. Ascomycin macrolactam derivative SDZ ASM 981 inhibits the release of granule-associated mediators and of newly synthesized cytokines in RBL 2H3 mast cells in an immunophilin-dependent manner.

    Science.gov (United States)

    Hultsch, T; Müller, K D; Meingassner, J G; Grassberger, M; Schopf, R E; Knop, J

    1998-09-01

    Mast cells play an important role in the pathological development of many inflammatory and allergic diseases and inhibition of mast cell activation is a potential target for therapeutic intervention. Therefore, the effect of the novel ascomycin macrolactam derivative SDZ ASM 981 on Fc epsilonRI-mediated activation of rat basophilic leukemia (RBL) cells, as a model for mast cell activation, was investigated. First, the ability to inhibit different mast cell immunophilins in vitro was tested. Using recombinant macrophilin-12 (FKBP-12), inhibition of rotamase activity with an IC50 of approximately 6 nM was observed. The rotamase activity of cyclophilin A (18 kDa) was not affected. Secondly, the effect of SDZ ASM 981 on Fc epsilonRI-mediated mast cell activation was investigated in the RBL cell model. SDZ ASM 981 inhibited exocytosis of preformed mediators (e.g. serotonin) with an IC50 of approximately 30 nM. Transcription and release of newly synthesized mediators (e.g. TNF-alpha) was inhibited with an IC50 of approximately 100 nM. The inhibitory effect of SDZ ASM 981 was antagonized by rapamycin. We conclude that SDZ ASM 981 is a potent inhibitor of Fc epsilonRI-mediated activation of mast cells in vitro. The mechanism of action involves formation of (calcineurin) inhibitory complexes with macrophilins. We suggest that this inhibitory action on mast cells might contribute to the antiinflammatory effect of SDZ ASM 981 observed in vivo (e.g. in aptopic dermatitis and psoriasis).

  11. Coding gaze tracking data with chromatic gradients for VR Exposure Therapy

    DEFF Research Database (Denmark)

    Herbelin, Bruno; Grillon, Helena; De Heras Ciechomski, Pablo

    2007-01-01

    This article presents a simple and intuitive way to represent the eye-tracking data gathered during immersive virtual reality exposure therapy sessions. Eye-tracking technology is used to observe gaze movements during vir- tual reality sessions and the gaze-map chromatic gradient coding allows to...... is fully compatible with different VR exposure systems and provides clinically meaningful data....

  12. CERN Technical Training 2004: New Short Course III (SC III) on Microsoft Outlook - Meetings and Delegation

    CERN Multimedia

    Monique Duval

    2004-01-01

    The CERN Technical Training programme is now proposing a new format for courses on Microsoft Outlook. Three two-hours Short Courses (SC) cover basic and advanced functionalities of the recommended mail client for email at CERN. Each module can be followed independently. The next scheduled session of the 3rd module will take place as follows: Outlook (SC III): Meetings and Delegation. Next session: 9.11.2004 (14:00-16:00) SC III will cover how to organise and manage meetings, work with meeting requests, share tasks, and use email and calendar delegation. The number of participants to each session is limited to 8. The instructor is English-French bilingual, and she will be available some time after each session to answer specific questions, or provide further explanations following demand. The cost of attending any SC module on Outlook is 70.- CHF. The above session will be confirmed if there are enough participants, and the attendance costs will be lower in case of a full class. If you are interested in...

  13. Bring out your codes! Bring out your codes! (Increasing Software Visibility and Re-use)

    Science.gov (United States)

    Allen, A.; Berriman, B.; Brunner, R.; Burger, D.; DuPrie, K.; Hanisch, R. J.; Mann, R.; Mink, J.; Sandin, C.; Shortridge, K.; Teuben, P.

    2013-10-01

    Progress is being made in code discoverability and preservation, but as discussed at ADASS XXI, many codes still remain hidden from public view. With the Astrophysics Source Code Library (ASCL) now indexed by the SAO/NASA Astrophysics Data System (ADS), the introduction of a new journal, Astronomy & Computing, focused on astrophysics software, and the increasing success of education efforts such as Software Carpentry and SciCoder, the community has the opportunity to set a higher standard for its science by encouraging the release of software for examination and possible reuse. We assembled representatives of the community to present issues inhibiting code release and sought suggestions for tackling these factors. The session began with brief statements by panelists; the floor was then opened for discussion and ideas. Comments covered a diverse range of related topics and points of view, with apparent support for the propositions that algorithms should be readily available, code used to produce published scientific results should be made available, and there should be discovery mechanisms to allow these to be found easily. With increased use of resources such as GitHub (for code availability), ASCL (for code discovery), and a stated strong preference from the new journal Astronomy & Computing for code release, we expect to see additional progress over the next few years.

  14. CERN Technical Training 2004: Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A 'blended learning' course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on November 9, morning. Course sessions are self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the appropriate WBT...

  15. Using ASM Podcasts to Excite Undergraduate Students about Current Microbiological Research

    Directory of Open Access Journals (Sweden)

    Stacey E. Lettini

    2014-08-01

    Full Text Available Innovative technology is often used as a mechanism to engage students in and out of the classroom and can be used to increase critical thinking skills. Podcasts are an excellent way to introduce students to current topics and research in microbiology. The American Society for Microbiology (ASM produces three podcasts that are microbiologically focused: This Week in Microbiology (TWiM, This Week in Parasitology (TWiP, and This Week in Virology (TWiV. These podcasts are usually presented in a manner similar to a journal club, as the presenters regularly invite guests to discuss current research papers. Since students often find reading scientific literature difficult and get bogged down in the details rather than seeing the over-arching purpose of a paper, these podcasts have been used in a General Microbiology course to introduce recent research articles. The students were first assigned an original research article to read and review, and they were asked to generate questions pertaining to things they did not understand. Next, students listened to the corresponding podcast that discussed the article and used it to answer their questions. This was followed by a classroom discussion of the article and the podcast. The ASM podcast helped to demystify original research by providing details of the experimental design and presentation of the results in a language that is more casual and relatable. Students demonstrated greater critical thinking and comprehension of microbiology literature after listening to the podcast. This activity can be used in a variety of courses in the biology curriculum.

  16. Look at the Gato! Code-Switching in Speech to Toddlers

    Science.gov (United States)

    Bail, Amelie; Morini, Giovanna; Newman, Rochelle S.

    2015-01-01

    We examined code-switching (CS) in the speech of twenty-four bilingual caregivers when speaking with their 18- to 24-month-old children. All parents CS at least once in a short play session, and some code-switched quite often (over 1/3 of utterances). This CS included both inter-sentential and intra-sentential switches, suggesting that at least…

  17. Ethical codes. Fig leaf argument, ballast or cultural element for radiation protection?

    International Nuclear Information System (INIS)

    Gellermann, Rainer

    2014-01-01

    The international association for radiation protection (IRPA) adopted in May 2004 a Code of Ethics in order to allow their members to hold an adequate professional level of ethical line of action. Based on this code of ethics the professional body of radiation protection (Fachverband fuer Strahlenschutz) has developed its own ethical code and adopted in 2005.

  18. Pipe elbow stiffness coefficients including shear and bend flexibility factors for use in direct stiffness codes

    International Nuclear Information System (INIS)

    Perry, R.F.

    1977-01-01

    Historically, developments of computer codes used for piping analysis were based upon the flexibility method of structural analysis. Because of the specialized techniques employed in this method, the codes handled systems composed of only piping elements. Over the past ten years, the direct stiffness method has gained great popularity because of its systematic solution procedure regardless of the type of structural elements composing the system. A great advantage is realized with a direct stiffness code that combines piping elements along with other structural elements such as beams, plates, and shells, in a single model. One common problem, however, has been the lack of an accurate pipe elbow element that would adequately represent the effects of transverse shear and bend flexibility factors. The purpose of the present paper is to present a systematic derivation of the required 12x12 stiffness matrix and load vectors for a three dimensional pipe elbow element which includes the effects of transverse shear and pipe bend flexibility according to the ASME Boiler and Pressure Vessel Code, Section III. The results are presented analytically and as FORTRAN subroutines to be directly incorporated into existing direct stiffness codes. (Auth.)

  19. Eficacia de la terapia de nebulización vs. inhalación con fenoterol en la crisis asmática moderada infantil, en el Hospital de Emergencias Pediátricas, año 2004

    OpenAIRE

    Ruiz Mori, Hernán Jorge

    2007-01-01

    La prevalencia de la crisis asmática se ha incrementado dramáticamente en la última década, constituyendo un problema de salud pública. El tratamiento de elección es el uso de broncodilatadores por vía inhalatoria, existiendo dos modalidades para administrar el broncodilatador: la Nebulización y la Inhalación. Hasta la actualidad hay controversias sobre la modalidad más eficaz, aquella que tiene una mejor respuesta clínica en el niño; siendo la nebulización la más utilizada. El objetivo de...

  20. Batse/Sax and Batse/RXTE-ASM Joint Spectral Studies of GRBs

    Science.gov (United States)

    Paciesas, William S.

    2002-01-01

    We proposed to make joint spectral analysis of gamma-ray bursts (GRBs) in the BATSE data base that are located within the fields of view of either the BeppoSAX wide field cameras (WFCs) or the RXTE all-sky monitor (ASM). The very broad-band coverage obtained in this way would facilitate various studies of GRB spectra that are difficult to perform with BATSE data alone. Unfortunately, the termination of the CGRO mission in June 2000 was not anticipated at the time of the proposal, and the sample of common events turned out to be smaller than we would have liked.

  1. SERPENT Monte Carlo reactor physics code

    International Nuclear Information System (INIS)

    Leppaenen, J.

    2010-01-01

    SERPENT is a three-dimensional continuous-energy Monte Carlo reactor physics burnup calculation code, developed at VTT Technical Research Centre of Finland since 2004. The code is specialized in lattice physics applications, but the universe-based geometry description allows transport simulation to be carried out in complicated three-dimensional geometries as well. The suggested applications of SERPENT include generation of homogenized multi-group constants for deterministic reactor simulator calculations, fuel cycle studies involving detailed assembly-level burnup calculations, validation of deterministic lattice transport codes, research reactor applications, educational purposes and demonstration of reactor physics phenomena. The Serpent code has been publicly distributed by the OECD/NEA Data Bank since May 2009 and RSICC in the U. S. since March 2010. The code is being used in some 35 organizations in 20 countries around the world. This paper presents an overview of the methods and capabilities of the Serpent code, with examples in the modelling of WWER-440 reactor physics. (Author)

  2. Structural integrity evaluation of nuclear piping cracket

    International Nuclear Information System (INIS)

    Cadiz Deleito, J.C.

    1985-01-01

    The methodology to evaluation of cracks in nuclear piping is exposed. Linear elastic fracture mechanic is used to prediction of growing crack and the net section collapse theory compared with acceptation criteria of both ASME III and ASME XI code. A case allowable under ASME XI criteria is analysed under ASME III requirements. Consideration must be given to local phenomenon in crack area and local stress evaluated and compared with ASME III acceptation criteria. (author)

  3. Session-RPE for quantifying load of different youth taekwondo training sessions.

    Science.gov (United States)

    Lupo, Corrado; Capranica, Laura; Cortis, Cristina; Guidotti, Flavia; Bianco, Antonino; Tessitore, Antonio

    2017-03-01

    The session rating of perceived exertion (session-RPE) proved to be a valuable method to quantify the internal training load (ITL) in taekwondo. However, no study validated this method in youth taekwondo athletes performing different training sessions. Thus this study aimed at evaluating the reliability of the session-RPE to monitor the ITL of prepubescent taekwondo athletes during pre-competitive (PC) and competitive (C) training sessions. Five female (age: 12.0±0.7 y; height: 1.54±0.08 m; body mass: 48.8±7.3 kg) and four male (age: 12.0±0.8 yrs; height: 1.55±0.07 m; body mass: 47.3±5.3 kg) taekwondo athletes were monitored during 100 individual sessions (PC: N.=33; C: N.=67). The Edwards' HR method was used as reference measure of ITL; the CR-10 RPE scale was administered at 1- and 30-minutes from the end of each session. No difference for gender emerged. The ITLs of C (Edwards: 228±40 arbitrary units, AU) resulted higher than that of PC (192±26 AU; P=0.04). Although all training typologies and data collections achieved significant correlations between Edwards' and session-RPE methods, a large relationship (r =0.71, Psessions evaluated at 30 minutes of the recovery phases. Findings support coaches of prepubescent taekwondo athletes to successfully use session-RPE to monitor the ITL of different training typologies. However, PC training evaluated at 30 minutes of the recovery phase represents the best condition for a highly reliable ITL perception.

  4. Assessing treatment integrity in cognitive-behavioral therapy: comparing session segments with entire sessions.

    Science.gov (United States)

    Weck, Florian; Grikscheit, Florian; Höfling, Volkmar; Stangier, Ulrich

    2014-07-01

    The evaluation of treatment integrity (therapist adherence and competence) is a necessary condition to ensure the internal and external validity of psychotherapy research. However, the evaluation process is associated with high costs, because therapy sessions must be rated by experienced clinicians. It is debatable whether rating session segments is an adequate alternative to rating entire sessions. Four judges evaluated treatment integrity (i.e., therapist adherence and competence) in 84 randomly selected videotapes of cognitive-behavioral therapy for major depressive disorder, social anxiety disorder, and hypochondriasis (from three different treatment outcome studies). In each case, two judges provided ratings based on entire therapy sessions and two on session segments only (i.e., the middle third of the entire sessions). Interrater reliability of adherence and competence evaluations proved satisfactory for ratings based on segments and the level of reliability did not differ from ratings based on entire sessions. Ratings of treatment integrity that were based on entire sessions and session segments were strongly correlated (r=.62 for adherence and r=.73 for competence). The relationship between treatment integrity and outcome was comparable for ratings based on session segments and those based on entire sessions. However, significant relationships between therapist competence and therapy outcome were only found in the treatment of social anxiety disorder. Ratings based on segments proved to be adequate for the evaluation of treatment integrity. The findings demonstrate that session segments are an adequate and cost-effective alternative to entire sessions for the evaluation of therapist adherence and competence. Copyright © 2014. Published by Elsevier Ltd.

  5. A Case for Dynamic Reverse-code Generation to Debug Non-deterministic Programs

    Directory of Open Access Journals (Sweden)

    Jooyong Yi

    2013-09-01

    Full Text Available Backtracking (i.e., reverse execution helps the user of a debugger to naturally think backwards along the execution path of a program, and thinking backwards makes it easy to locate the origin of a bug. So far backtracking has been implemented mostly by state saving or by checkpointing. These implementations, however, inherently do not scale. Meanwhile, a more recent backtracking method based on reverse-code generation seems promising because executing reverse code can restore the previous states of a program without state saving. In the literature, there can be found two methods that generate reverse code: (a static reverse-code generation that pre-generates reverse code through static analysis before starting a debugging session, and (b dynamic reverse-code generation that generates reverse code by applying dynamic analysis on the fly during a debugging session. In particular, we espoused the latter one in our previous work to accommodate non-determinism of a program caused by e.g., multi-threading. To demonstrate the usefulness of our dynamic reverse-code generation, this article presents a case study of various backtracking methods including ours. We compare the memory usage of various backtracking methods in a simple but nontrivial example, a bounded-buffer program. In the case of non-deterministic programs such as this bounded-buffer program, our dynamic reverse-code generation outperforms the existing backtracking methods in terms of memory efficiency.

  6. Performance study of K{sub e} factors in simplified elastic plastic fatigue analyses with emphasis on thermal cyclic loading

    Energy Technology Data Exchange (ETDEWEB)

    Lang, Hermann, E-mail: hermann.lang@areva.com [AREVA NP GmbH, PEEA-G, Henri-Dunant-Strasse 50, 91058 Erlangen (Germany); Rudolph, Juergen; Ziegler, Rainer [AREVA NP GmbH, PEEA-G, Henri-Dunant-Strasse 50, 91058 Erlangen (Germany)

    2011-08-15

    As code-based fully elastic plastic code conforming fatigue analyses are still time consuming, simplified elastic plastic analysis is often applied. This procedure is known to be overly conservative for some conditions due to the applied plastification (penalty) factor K{sub e}. As a consequence, less conservative fully elastic plastic fatigue analyses based on non-linear finite element analyses (FEA) or simplified elastic plastic analysis based on more realistic K{sub e} factors have to be used for fatigue design. The demand for more realistic K{sub e} factors is covered as a requirement of practical fatigue analysis. Different code-based K{sub e} procedures are reviewed in this paper with special regard to performance under thermal cyclic loading conditions. Other approximation formulae such as those by Neuber, Seeger/Beste or Kuehnapfel are not evaluated in this context because of their applicability to mechanical loading excluding thermal cyclic loading conditions typical for power plant operation. Besides the current code-based K{sub e} corrections, the ASME Code Case N-779 (e.g. Adam's proposal) and its modification in ASME Section VIII is considered. Comparison of elastic plastic results and results from the Rules for Nuclear Facility Components and Rules for Pressure Vessels reveals a considerable overestimation of usage factor in the case of ASME III and KTA 3201.2 for the examined examples. Usage factors according to RCC-M, Adams (ASME Code Case N-779), ASME VIII (alternative) and EN 13445-3 are essentially comparable and less conservative for these examples. The K{sub v} correction as well as the applied yield criterion (Tresca or von Mises) essentially influence the quality of the more advanced plasticity corrections (e.g. ASME Code Case N-779 and RCC-M). Hence, new proposals are based on a refined K{sub v} correction.

  7. Performance study of Ke factors in simplified elastic plastic fatigue analyses with emphasis on thermal cyclic loading

    International Nuclear Information System (INIS)

    Lang, Hermann; Rudolph, Juergen; Ziegler, Rainer

    2011-01-01

    As code-based fully elastic plastic code conforming fatigue analyses are still time consuming, simplified elastic plastic analysis is often applied. This procedure is known to be overly conservative for some conditions due to the applied plastification (penalty) factor K e . As a consequence, less conservative fully elastic plastic fatigue analyses based on non-linear finite element analyses (FEA) or simplified elastic plastic analysis based on more realistic K e factors have to be used for fatigue design. The demand for more realistic K e factors is covered as a requirement of practical fatigue analysis. Different code-based K e procedures are reviewed in this paper with special regard to performance under thermal cyclic loading conditions. Other approximation formulae such as those by Neuber, Seeger/Beste or Kuehnapfel are not evaluated in this context because of their applicability to mechanical loading excluding thermal cyclic loading conditions typical for power plant operation. Besides the current code-based K e corrections, the ASME Code Case N-779 (e.g. Adam's proposal) and its modification in ASME Section VIII is considered. Comparison of elastic plastic results and results from the Rules for Nuclear Facility Components and Rules for Pressure Vessels reveals a considerable overestimation of usage factor in the case of ASME III and KTA 3201.2 for the examined examples. Usage factors according to RCC-M, Adams (ASME Code Case N-779), ASME VIII (alternative) and EN 13445-3 are essentially comparable and less conservative for these examples. The K v correction as well as the applied yield criterion (Tresca or von Mises) essentially influence the quality of the more advanced plasticity corrections (e.g. ASME Code Case N-779 and RCC-M). Hence, new proposals are based on a refined K v correction.

  8. Nuclear medical inpatient treatment in Germany. Analysis of the structured quality reports 2004 to 2008; Stationaere nuklearmedizinische Therapie in Deutschland. Analyse der strukturierten Qualitaetsberichte 2004 bis 2008

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz, R.; Reiners, C. [Universitaetsklinikum Wuerzburg (Germany). Klinik und Poliklinik fuer Nuklearmedizin; Dietlein, M. [Koeln Univ. (Germany). Klinik und Poliklinik fuer Nuklearmedizin

    2010-07-01

    All public licensed hospitals of Germany are obligated since 2004 to establish and to publish a structured biennial quality report. The aim of this study was to analyse the quality reports from 2008 of clinics with nuclear-medicine therapy ward and to investigate developments for the inpatient nuclear-medicine therapy by comparing the results with the quality reports of the years 2004 and 2006. Methods: All available structured quality reports of clinics with a nuclear-medicine therapy ward of the years 2004, 2006 and 2008 were evaluated. Results: The total number of inpatient treatment cases in 2008 amounted to 54 190 (2006: 54 884; 2004: 57 366). This corresponds to a decrease of 5.5% in comparison to 2004. The number of the therapy wards decreased at the same time to currently 117 (2006: 120; 2004: 124). Remarkable changes were found in the spectrum of the main diagnosis. Thus, the most frequent diagnosis with the ICD-code E05 (hyperthyroidism) decreased continuously from 37 747 treatments in 2004 and 34 764 in 2006 to 31 756 in the year 2008. In contrast, the ICD-diagnoses for thyroid cancer (C73, Z08) with 14 761 cases in 2008 increased with time (2006: 13 426; 2004: 12 581). Conclusions: In analogy to the observations from Europe after introduction of an iodine prophylaxis the improved iodine supply in Germany has led to a decline of the radioiodine therapy due to hyperthyroidism.

  9. Intervención educativa para población infanto-juvenil asmática

    Directory of Open Access Journals (Sweden)

    Maria Antonia Acevedo Veja

    2015-11-01

    Full Text Available Se realizó una intervención educativa a la población infanto-juvenil asmática con edades entre ocho y once años en el policlínico de Manatí, Las Tunas, entre enero y julio de 2012, con el objetivo de evaluar la eficacia de la misma. La población de estudio estuvo formada por los 258 pacientes asmáticos de los 29 Consultorios de Médico de Familia (CMF del área, y la muestra por los 50 seleccionados por muestreo aleatorio simple. La información se obtuvo mediante un cuestionario que fue aplicado antes y después de la intervención educativa y los datos fueron recogidos durante la consulta y de la historia clínica individual. Se concluyó que predominó el sexo masculino, con antecedentes de primera línea de asma bronquial, con factores desencadenantes tales como: infecciones respiratorias agudas, polvo y humedad, así como aquellos que presentan signos clínicos de reflujo y que tienen una mala técnica de aplicación de spray. Se apreció un insuficiente nivel de conocimientos sobre la evaluación de severidad de la crisis, los factores desencadenantes, el manejo del spray y el tratamiento intercrisis, y las exacerbaciones.

  10. Technical Training: CERN Technical Training 2004 - Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on 7 September, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office XP' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the app...

  11. Technical Training: CERN Technical Training 2004 - Instructor-led WBTechT Course for Microsoft Applications

    CERN Multimedia

    Monique Duval

    2004-01-01

    Would you need to enhance your skills in Microsoft Office applications or Outlook? A new blended learning course, combining instructor-led and computer-based multimedia training, is now offered by Technical Training: the Instructor-led CERN Web-Based Technical Training (WBTechT) Course for Microsoft Applications. The next session will take place on September 7, morning. Course sessions will be self-paced and self-directed, with participants being in control of their learning, while having direct access to an instructor when in class. Topics include the Microsoft Office XP suite (Word, Excel, PowerPoint, Access) and Outlook, at introductory, intermediate and advanced levels. Visit the 2004 CERN WBTechT Portal, http://www.course-source.net/sites/cern/, where you can find the detailed course contents under the 'Microsoft Office XP' catalogue. Previous experience in web-based training is not required, as each session will start with an introduction to E-learning, and registration of the participants into the ...

  12. Formal description of the OSI session layer: session service

    NARCIS (Netherlands)

    van Sinderen, Marten J.; van Eijk, P.H.J.; Vissers, C.A.; Diaz, M.

    1989-01-01

    The LOTOS formal description of the OSI session service is presented on basis of specification samples from the full description, giving account of how specification styles and session service architectural elements are reflected in the description. Both information (data types) and process

  13. Auriculoterapia en pacientes asmáticos

    Directory of Open Access Journals (Sweden)

    Adolfo González Salvador

    1997-04-01

    Full Text Available Se realiza un estudio para evaluar la eficacia de la auriculopuntura en 30 asmáticos del área de salud de Aguada de Pasajeros, durante los meses de noviembre de 1992 a abril de 1993. El tratamiento se aplicó durante un mes, con seguimiento durante los 5 meses posteriores. Se observó una disminución en la frecuencia, intensidad y duración de las crisis de asma; la mayoría de los pacientes tuvo una evolución satisfactoria y no se presentaron complicaciones. Se concluye que la auriculoterapia es un método útil en pacientes con asma bronquial debido a su eficacia e inocuidadA study was conducted to evaluate the efficacy of auriculopuncture in 30 asthmatic patients from the health area of Aguada de Pasajeros between November, 1992, and April, 1993. The treatment was applied for a month, with a follow-up during the next 5 months. It was observed a reduction in the frequency, intensity and duration of the asthma crises. Most of the patients had a satisfactory evolution and there were no complications. It is concluded that auriculotherapy is a useful method for patients with bronchial asthma due to its effectiveness and innocuousness.

  14. What we heard within WPDD on stakeholder involvement in decommissioning, 2001-2004. A Compilation of Papers

    International Nuclear Information System (INIS)

    2006-01-01

    At its sixth meeting, the WPDD held a topical session on Stakeholder Involvement in Decommissioning Projects. The topical session was jointly planned and run with members of the NEA Forum on Stakeholder Confidence (FSC). The Topical Session provided a stimulus to review the contributions in the area of stakeholder involvement that the WPDD have received since its inception. This report contains a compilation of all papers regarding stakeholder involvement in decommissioning given at WPDD meetings and workshops between 2001 and the end of 2004. The compilation, together with other relevant material collected by FSC, will serve as background material for a review, focusing on lessons to be learnt and including examples of key statements by representatives from different NEA member states involved in or affected by decommissioning projects. The review is intended to be published during 2006 in a NEA brochure

  15. A Retrospective Look at 20 Years of ASM Education Programs (1990-2010) and a Prospective Look at the Next 20 Years (2011-2030).

    Science.gov (United States)

    Chang, Amy

    2011-01-01

    Professional societies provide visibility and legitimacy to the work of their post secondary educator members, advocate best practices in courses and sponsored student research, and establish deep networks and communities that catalyze members to collectively engage in undergraduate teaching and learning scholarship. Within the American Society for Microbiology (ASM), the Education Board, established in the mid-1970s, assumes this role. I have been fortunate enough to watch several pivotal programs support our growth and change the status quo by providing opportunities for biology educators to flourish. In this retrospective review, the background and details I offer about each initiative help explain ASM Education offerings, how our growth has been supported and how the status quo has changed. In this prospective look, I offer my vision of the future in post secondary education where classroom learning is student-centered and focused on global problems affecting our health and environment. For the profession to proliferate, the ASM must provide members as many opportunities in learning biology as they do with advancing biology to new frontiers.

  16. Challenge - converting to ANSI/ASME NQA Standard 1

    International Nuclear Information System (INIS)

    Nansen, J.N.

    1983-03-01

    Prior to August, 1980, Westinghouse Hanford Company operated the Hanford Engineering Development Laboratory Quality Program in accordance with the requirements of RDT F 2-2T and RDT F 2-4T and for a short while to ANSI N45.2. Following the issuance of the national consensus standard ANSI/ ASME NQA Standard 1 in August 1979, and its acceptance by DOE, the Laboratory began making changes to meet these requirements in its internal quality program in August 1980. This was followed with the invoking of these requirements on supplier's programs and all procurement activities in March of 1981. This conversion was completed in approximately six months and provided an opportunity for several improvements. The keynote of this standard is flexibility. A major improvement noted was in the flexibility of application. The program can be tailored to meet specific needs. Vendor surveys under NQA-1 have shown positive results in that the organization and structure of the standard is much easier to follow and understand

  17. Meeting report on the ASM Conference on Mechanisms of Interbacterial Cooperation and Competition.

    Science.gov (United States)

    Lories, Bram; Parijs, Ilse; Foster, Kevin R; Steenackers, Hans P

    2017-08-14

    The ASM Conference on Mechanisms of Interbacterial Cooperation and Competition was held in Washington DC, from 1 to 4 March 2017. The conference provided an international forum for sociomicrobiologists from different disciplines to present and discuss new findings. The meeting covered a wide range of topics, spanning molecular mechanisms, ecology, evolution, computation and manipulation of interbacterial interactions, and encompassed social communities in medicine, the natural environment, and industry. This report summarizes the presentations and emerging themes. Copyright © 2017 American Society for Microbiology.

  18. Kartlegging av astmaundervisning til barn og foreldre i barneavdelinger mellom 2004, 2006 og 2014

    Directory of Open Access Journals (Sweden)

    Anne Trollvik

    2017-06-01

    Full Text Available The aim of the study was to investigate the organization of asthma education for children and parents in children’s wards in Norway over a ten-year period and how Ane and Bronky teaching material has been implemented. A prospective cross-sectional study using a questionnaire was conducted in 28, 22 and 29 children’s wards in 2004, 2006 and 2014. The response rate varied between 86 percent and 97 percent. Statistical analysis by means of Fisher’s exact test was used. The findings revealed that organized asthma education for children increased between 2004 and 2006, while it decreased in 2014. Dialogue and demonstration were common teaching methods. User participation in teaching sessions increased between 2004 and 2006. Only half of the wards reported that asthma education was the responsibility of management to a large/very large extent. This presents future challenges in establishing, prioritizing and ensuring stability in health education for children and their families.

  19. Annual results 2004; Resultats annuels 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This 2004 annual evaluation of the french RTE company (electric power transport network) provides information on the 2004 results on: institutional information, financial results, customers and market, industrial resources, environment and consultation, human resources and international aspects. (A.L.B.)

  20. Single-session Gamma Knife radiosurgery for optic pathway/hypothalamic gliomas.

    Science.gov (United States)

    El-Shehaby, Amr M N; Reda, Wael A; Abdel Karim, Khaled M; Emad Eldin, Reem M; Nabeel, Ahmed M

    2016-12-01

    OBJECTIVE Because of their critical and central location, it is deemed necessary to fractionate when considering irradiating optic pathway/hypothalamic gliomas. Stereotactic fractionated radiotherapy is considered safer when dealing with gliomas in this location. In this study, the safety and efficacy of single-session stereotactic radiosurgery for optic pathway/hypothalamic gliomas were reviewed. METHODS Between December 2004 and June 2014, 22 patients with optic pathway/hypothalamic gliomas were treated by single-session Gamma Knife radiosurgery. Twenty patients were available for follow-up for a minimum of 1 year after treatment. The patients were 5 to 43 years (median 16 years) of age. The tumor volume was 0.15 to 18.2 cm 3 (median 3.1 cm 3 ). The prescription dose ranged from 8 to 14 Gy (median 11.5 Gy). RESULTS The mean follow-up period was 43 months. Five tumors involved the optic nerve only, and 15 tumors involved the chiasm/hypothalamus. Two patients died during the follow-up period. The tumors shrank in 12 cases, remained stable in 6 cases, and progressed in 2 cases, thereby making the tumor control rate 90%. Vision remained stable in 12 cases, improved in 6 cases, and worsened in 2 cases in which there was tumor progression. Progression-free survival was 83% at 3 years. CONCLUSIONS The initial results indicate that single-session Gamma Knife radiosurgery is a safe and effective treatment option for optic pathway/hypothalamic gliomas.

  1. Gap Analysis of Material Properties Data for Ferritic/Martensitic HT-9 Steel

    International Nuclear Information System (INIS)

    Brown, Neil R.; Serrano De Caro, Magdalena; Rodriguez, Edward A.

    2012-01-01

    The US Department of Energy (DOE), Office of Nuclear Energy (NE), is supporting the development of an ASME Code Case for adoption of 12Cr-1Mo-VW ferritic/martensitic (F/M) steel, commonly known as HT-9, primarily for use in elevated temperature design of liquid-metal fast reactors (LMFR) and components. In 2011, Los Alamos National Laboratory (LANL) nuclear engineering staff began assisting in the development of a small modular reactor (SMR) design concept, previously known as the Hyperion Module, now called the Gen4 Module. LANL staff immediately proposed HT-9 for the reactor vessel and components, as well as fuel clad and ducting, due to its superior thermal qualities. Although the ASME material Code Case, for adoption of HT-9 as an approved elevated temperature material for LMFR service, is the ultimate goal of this project, there are several key deliverables that must first be successfully accomplished. The most important key deliverable is the research, accumulation, and documentation of specific material parameters; physical, mechanical, and environmental, which becomes the basis for an ASME Code Case. Time-independent tensile and ductility data and time-dependent creep and creep-rupture behavior are some of the material properties required for a successful ASME Code case. Although this report provides a cursory review of the available data, a much more comprehensive study of open-source data would be necessary. This report serves three purposes: (a) provides a list of already existing material data information that could ultimately be made available to the ASME Code, (b) determines the HT-9 material properties data missing from available sources that would be required and (c) estimates the necessary material testing required to close the gap. Ultimately, the gap analysis demonstrates that certain material properties testing will be required to fulfill the necessary information package for an ASME Code Case.

  2. Evaluation of local allowable wall thickness of thinned pipe considering internal pressure and bending moment

    International Nuclear Information System (INIS)

    Kim, J. W.; Park, C. Y.; Kim, B. Y.

    2000-01-01

    This study proposed the local allowable wall thickness (LAWT) evaluation method for local wall thinned pipe subjected by internal pressure and bending moment. Also, LAWT was evaluated for simplified thinned pipe and the effect of axial extent of thinned area on LAWT was investigated. The results showed that LAWT predicted by present method was thinner, about 50%, than that evaluated by construction code and ASME Code Case N-597, while it was thicker, about 2 times, than that calculated by evaluation model based on pipe experiments. LAWT decreased with increasing axial extent of thinned area and was saturated above axial extent of pipe radius, which was a contrast to the results of ASME Code Case N-597 evaluation. The results of stress analysis with applied loading type indicated that the effect of axial extent of thinned area on LAWT was dependent on loading type considering in the evaluation. That is, the dependence of axial extent on LAWT is determined by magnitude of bending moment, and the contrary trend with axial extent in ASME Code Case is because ASME Code Case N-597 considers only internal pressure in the evaluation

  3. Providing thermal-hydraulic boundary conditions to the reactor code TINTE through a Flownex-TINTE coupling - HTR2008-58110

    International Nuclear Information System (INIS)

    Marais, D.; Greyvenstein, G. P.

    2008-01-01

    TINTE is a well established reactor analysis code which models the transient behaviour of pebble bed reactor cores but it does not include the capabilities to model a power conversion unit (PCU). This raises the issue that TINTE cannot model full system transients. One way to overcome this problem is to supply TINTE with time-dependant thermal-hydraulic boundary conditions which are obtained from PCU simulations. This study investigates a method to provide boundary conditions for the nuclear code TINTE during full system transients. This was accomplished by creating a high level interface between the systems CFD code Flownex and TINTE. An indirect coupling method is explored whereby characteristics of the PCU are matched to characteristics of the nuclear core. This method eliminates the need to iterate between the two codes. A number of transients are simulated using the coupled code and then compared against stand-alone Flownex simulations. The coupling method introduces relatively small errors when reproducing mass flow, temperature and pressure in steady state analysis, but become more pronounced when dealing with fast thermal-hydraulic transients. Decreasing the maximum time step length of TINTE reduces this problem, but increases the computational time. Copyright ASME 2008. (authors)

  4. Characterization of Centrifugally-Loaded Flame Migration for Ultra-Compact Combustors

    Science.gov (United States)

    2011-10-01

    configuration on the flat vane. However, Radtke [38] investigated a curved radial vane geometry and demonstrated increased combustion eciency with the curved...Hancock, R. D., “Ultra-Compact Combustors for Advanced Gas Turbine Engines,” ASME Turbo Expo 2004 , GT-2004-53155, 2004. [38] Radtke , J. T., Eciency

  5. Safety Evaluation Report, pump and valve inservice testing program, Yankee Rowe Nuclear Power Station (Docket No. 50-29). Revision 1

    International Nuclear Information System (INIS)

    Ransom, C.B.; Rockhold, H.C.

    1985-10-01

    The staff reviewed the Yankee Rowe IST program submittal dated October 2, 1981 and evaluated the proposed tests for compliance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, 1977 Edition, through the Summer of 1978 Addenda. Those items not in compliance were discussed in a working session with Yankee Atomic Electric Company personnel, USNRC representatives, and EG and G Idaho reviewers on June 22, 1982. The evaluations presented in this SER of the Yankee Rowe pump and valve inservice testing program and the associated relief requests are those of the NRC staff. These findings apply only to component testing

  6. ASME N510 test results for Savannah River Site AACS filter compartments

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J.D.; Punch, T.M. [Westinghouse Savannah River Company, Aiken, SC (United States)

    1995-02-01

    The K-Reactor at the Savannah River Site recently implemented design improvements for the Airborne Activity Confinement System (AACS) by procuring, installing, and testing new Air Cleaning Units, or filter compartments, to ASME AG-11, N509, and N510 requirements. Specifically, these new units provide documentable seismic resistance to a Design Basis Accident earthquake, provide 2 inch adsorber beds with 0.25 second residence time, and meet all AG-1, N509, and N510 requirements for testability and maintainability. This paper presents the results of the Site acceptance testing and discusses an issue associated with sample manifold qualification testing.

  7. Evaluation of an interactive, case-based review session in teaching medical microbiology.

    Science.gov (United States)

    Blewett, Earl L; Kisamore, Jennifer L

    2009-08-27

    Oklahoma State University-Center for Health Sciences (OSU-CHS) has replaced its microbiology wet laboratory with a variety of tutorials including a case-based interactive session called Microbial Jeopardy!. The question remains whether the time spent by students and faculty in the interactive case-based tutorial is worthwhile? This study was designed to address this question by analyzing both student performance data and assessing students' perceptions regarding the tutorial. Both quantitative and qualitative data were used in the current study. Part One of the study involved assessing student performance using archival records of seven case-based exam questions used in the 2004, 2005, 2006, and 2007 OSU-CHS Medical Microbiology course. Two sample t-tests for proportions were used to test for significant differences related to tutorial usage. Part Two used both quantitative and qualitative means to assess student's perceptions of the Microbial Jeopardy! session. First, a retrospective survey was administered to students who were enrolled in Medical Microbiology in 2006 or 2007. Second, responses to open-ended items from the 2008 course evaluations were reviewed for comments regarding the Microbial Jeopardy! session. Both student performance and student perception data support continued use of the tutorials. Quantitative and qualitative data converge to suggest that students like and learn from the interactive, case-based session. The case-based tutorial appears to improve student performance on case-based exam questions. Additionally, students perceived the tutorial as helpful in preparing for exam questions and reviewing the course material. The time commitment for use of the case-based tutorial appears to be justified.

  8. Post-Session Authentication

    OpenAIRE

    Ahmed , Naveed; Jensen , Christian ,

    2012-01-01

    Part 1: Full Papers; International audience; Entity authentication provides confidence in the claimed identity of a peer entity, but the manner in which this goal is achieved results in different types of authentication. An important factor in this regard is the order between authentication and the execution of the associated session. In this paper, we consider the case of post-session authentication, where parties authenticate each other at the end of their interactive session. This use of a...

  9. Anaphora in question-answer sessions in university ELF contexts.

    Directory of Open Access Journals (Sweden)

    Thomas Wulstan Christiansen

    2015-07-01

    Full Text Available Abstract - Identity chains (Hasan 1984 ˗ strings of co-referential noun phrases ˗ constitute a lesser researched area in the field of ELF, as has the more general area of cohesion (but see Hüttner 2009, Christiansen 2011. Following on the work on anaphora of such scholars as Reinhart (1983 and Cornish (1999, and on cohesion (e.g. Halliday and Hasan 1976, Halliday 2004, Christiansen (2009a/b, 2011 focuses on the link between text cohesion and discourse coherence. The interactive perspective of discourse (seen as the process of which text is the product: see Widdowson 1984: 100 is especially relevant to an ELF context of spontaneous spoken interaction. As Guido (2008 evidences, different inter-cultural concerns constitute a crucial dimension to the complex multi-code interaction. Consequently, the diverse ways in which speakers from different L1 backgrounds employ anaphors and construct identity chains are key elements in the co-construction of a dialogic text. In this case study, six extracts of transcripts taken from the VOICE corpus (2011 of conference question and answer sessions set in multicultural contexts are analysed qualitatively. The different ways that participants construct identity chains (e.g. whether they use full forms of various kinds or anaphoric pro-forms are classified. The analysis focuses on both how individual anaphors are resolved and how relations between anaphors and antecedent triggers are encoded, and how identity chains are constructed and organized individually. The objective is to identify which kinds of noun phrase (various subtypes of full and pro-forms are used by diverse groups of EFL speakers both in relation to their own contributions and to those of other speakers (with a threefold distinction made between the same turn of the same speaker, a different turn of the same speaker, and a different turn by a different speaker.

  10. The Development of the World Anti-Doping Code.

    Science.gov (United States)

    Young, Richard

    2017-01-01

    This chapter addresses both the development and substance of the World Anti-Doping Code, which came into effect in 2003, as well as the subsequent Code amendments, which came into effect in 2009 and 2015. Through an extensive process of stakeholder input and collaboration, the World Anti-Doping Code has transformed the hodgepodge of inconsistent and competing pre-2003 anti-doping rules into a harmonized and effective approach to anti-doping. The Code, as amended, is now widely recognized worldwide as the gold standard in anti-doping. The World Anti-Doping Code originally went into effect on January 1, 2004. The first amendments to the Code went into effect on January 1, 2009, and the second amendments on January 1, 2015. The Code and the related international standards are the product of a long and collaborative process designed to make the fight against doping more effective through the adoption and implementation of worldwide harmonized rules and best practices. © 2017 S. Karger AG, Basel.

  11. Buckling rules in design codes: state of the art and future developments

    Energy Technology Data Exchange (ETDEWEB)

    Turbat, A. [FRAMATOME ANP, 69 - Lyon (France); Meziere, Y. [Electricite de France (EDF SEPTEN), 69 - Villeurbanne (France)

    2001-07-01

    Buckling, which can affect structures like bars, beams and shells when they are submitted to compressive stresses, can lead to unacceptable deformations and ruptures. Consequently, main Design Codes, especially those used in nuclear industry, include rules and analysis methods in order to prevent this phenomenon. In this paper, a review of buckling rules and/or analysis methods existing in ASME, RCC-M, RCC-MR and European Recommendations is performed. Then, these rules and methods are applied to the case of a cylinder filled with water and submitted to a seismic loading and results are compared. In the last part, current developments of methods to analyse creep buckling and dynamic buckling which should come and complete RCC-MR soon are presented. (author)

  12. Buckling rules in design codes: state of the art and future developments

    International Nuclear Information System (INIS)

    Turbat, A.; Meziere, Y.

    2001-01-01

    Buckling, which can affect structures like bars, beams and shells when they are submitted to compressive stresses, can lead to unacceptable deformations and ruptures. Consequently, main Design Codes, especially those used in nuclear industry, include rules and analysis methods in order to prevent this phenomenon. In this paper, a review of buckling rules and/or analysis methods existing in ASME, RCC-M, RCC-MR and European Recommendations is performed. Then, these rules and methods are applied to the case of a cylinder filled with water and submitted to a seismic loading and results are compared. In the last part, current developments of methods to analyse creep buckling and dynamic buckling which should come and complete RCC-MR soon are presented. (author)

  13. Probing the Mysteries of the X-Ray Binary 4U 1210-64 with ASM, MAXI and Suzaku

    Science.gov (United States)

    Coley, Joel B.; Corbet, R.; Mukai, K.; Pottschmidt, K.

    2013-01-01

    Optical and X-ray observations of 4U 1210-64 (1ES 1210-646) suggest that the source is a High Mass X-ray Binary (HMXB) probably powered by the Be mechanism. Data acquired by the RXTE All Sky Monitor (ASM), the ISS Monitor of All-sky X-ray Image (MAXI) and Suzaku provide a detailed temporal and spectral description of this poorly understood source. Long-term data produced by ASM and MAXI indicate that the source shows two distinct high and low states. A 6.7-day orbital period of the system was found in folded light curves produced by both ASM and MAXI. A two day Suzaku observation in Dec. 2010 took place during a transition from the minimum to the maximum of the folded light curve. The two day Suzaku observation reveals large variations in flux indicative of strong orbit to orbit variability. Flares in the Suzaku light curve can reach nearly 1.4 times the mean count rate. From a spectral analysis of the Suzaku data, emission lines in the Fe K alpha region were detected at 6.4 keV, 6.7 keV and 6.97 keV interpreted as FeI, FeXXV and FeXXVI. In addition, emission lines were observed at approximately 1.0 and 2.6 keV, corresponding to NeX and SXVI respectively. Thermal bremsstrahlung or power law models both modified by interstellar and partially covering absorption provide a good fit to the continuum data. This source is intriguing for these reasons: i) No pulse period was observed; ii) 6.7 day orbital period is much less than typical orbital periods seen in Be/X-ray Binaries; iii) The optical companion is a B5V--an unusual spectral class for an HMXB; iv) There are extended high and low X-ray states.

  14. The effects of age at photostimulation of male broiler breeders on ...

    African Journals Online (AJOL)

    User

    photostimulation, and dissipation of photorefractoriness was delayed so that birds matured at the same rate - as if they had been maintained on long days from hatch, as the delay in ASM was similar to the delay seen in females reared on 16 h light (Lewis et al., 2004). An advance in ASM was observed when females were.

  15. A practical approach for implementing risk-based inservice testing of pumps at nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, R.S.; Maret, D.; Seniuk, P.; Smith, L.

    1996-01-01

    The American Society of Mechanical Engineers (ASME) Center for Research and Technology Development's (CRTD) Research Task Force on Risk-Based Inservice Testing has developed guidelines for risk-based inservice testing (IST) of pumps and valves. These guidelines are intended to help the ASME Operation and Maintenance (OM) Committee to enhance plant safety while focussing appropriate testing resources on critical components. This paper describes a practical approach for implementing those guidelines for pumps at nuclear power plants. The approach, as described in this paper, relies on input, direction, and assistance from several entities such as the ASME Code Committees, United States Nuclear Regulatory Commission (NRC), and the National Laboratories, as well as industry groups and personnel with applicable expertise. Key parts of the risk-based IST process that are addressed here include: identification of important failure modes, identification of significant failure causes, assessing the effectiveness of testing and maintenance activities, development of alternative testing and maintenance strategies, and assessing the effectiveness of alternative testing strategies with present ASME Code requirements. Finally, the paper suggests a method of implementing this process into the ASME OM Code for pump testing

  16. A practical approach for implementing risk-based inservice testing of pumps at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, R.S. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Maret, D.; Seniuk, P.; Smith, L.

    1996-12-01

    The American Society of Mechanical Engineers (ASME) Center for Research and Technology Development`s (CRTD) Research Task Force on Risk-Based Inservice Testing has developed guidelines for risk-based inservice testing (IST) of pumps and valves. These guidelines are intended to help the ASME Operation and Maintenance (OM) Committee to enhance plant safety while focussing appropriate testing resources on critical components. This paper describes a practical approach for implementing those guidelines for pumps at nuclear power plants. The approach, as described in this paper, relies on input, direction, and assistance from several entities such as the ASME Code Committees, United States Nuclear Regulatory Commission (NRC), and the National Laboratories, as well as industry groups and personnel with applicable expertise. Key parts of the risk-based IST process that are addressed here include: identification of important failure modes, identification of significant failure causes, assessing the effectiveness of testing and maintenance activities, development of alternative testing and maintenance strategies, and assessing the effectiveness of alternative testing strategies with present ASME Code requirements. Finally, the paper suggests a method of implementing this process into the ASME OM Code for pump testing.

  17. Pressure vessel code construction capabilities for a nickel-chromium-tungsten-molybdenum alloy

    International Nuclear Information System (INIS)

    Rothman, M.F.

    1990-01-01

    HAYNES alloy 230 (UNS NO6230) has achieved wide usage in a variety of high-temperature aerospace, chemical process industry and industrial heating applications since its introduction in 1981. Combining high elevated temperature strength with excellent metallurgical stability, environment-resistance and relatively straight forward fabrication characteristics, this Ni-Cr-W-Mo alloy was an excellent candidate for ASME Pressure vessel Code applications. Coverage under case No. 2063 was granted in July, 1989, for both Section I and Section VIII Division 1 construction. In this paper, the metallurgy of 230 alloy will be described, and its design strength capabilities contrasted with those for more established code materials. Other important performance capabilities, such as long-term thermal stability, oxidation-resistance, fatigue-resistance, and resistance to other forms of environmental degradation will be discussed. It will be shown that the combined properties of 230 alloy offer some significant advantages over other materials for applications such as expansion bellows, heat-exchangers, valves and other components in the fossil energy, nuclear energy and chemical process industries, among others

  18. Numerical analysis and nuclear standard code application to thermal fatigue

    International Nuclear Information System (INIS)

    Merola, M.

    1992-01-01

    The present work describes the Joint Research Centre Ispra contribution to the IAEA benchmark exercise 'Lifetime Behaviour of the First Wall of Fusion Machines'. The results of the numerical analysis of the reference thermal fatigue experiment are presented. Then a discussion on the numerical analysis of thermal stress is tackled, pointing out its particular aspects in view of their influence on the stress field evaluation. As far as the design-allowable number of cycles are concerned the American nuclear code ASME and the French code RCC-MR are applied and the reasons for the different results obtained are investigated. As regards a realistic fatigue lifetime evaluation, the main problems to be solved are brought out. This work, is intended as a preliminary basis for a discussion focusing on the main characteristics of the thermal fatigue problem from both a numerical and a lifetime assessment point of view. In fact the present margin of discretion left to the analyst may cause undue discrepancies in the results obtained. A sensitivity analysis of the main parameters involved is desirable and more precise design procedures should be stated

  19. Evaluation of temporary non-code repairs in safety class 3 piping systems

    International Nuclear Information System (INIS)

    Godha, P.C.; Kupinski, M.; Azevedo, N.F.

    1996-01-01

    Temporary non-ASME Code repairs in safety class 3 pipe and piping components are permissible during plant operation in accordance with Nuclear Regulatory Commission Generic Letter 90-05. However, regulatory acceptance of such repairs requires the licensee to undertake several timely actions. Consistent with the requirements of GL 90-05, this paper presents an overview of the detailed evaluation and relief request process. The technical criteria encompasses both ductile and brittle piping materials. It also lists appropriate evaluation methods that a utility engineer can select to perform a structural integrity assessment for design basis loading conditions to support the use of temporary non-Code repair for degraded piping components. Most use of temporary non-code repairs at a nuclear generating station is in the service water system which is an essential safety related system providing the ultimate heat sink for various plant systems. Depending on the plant siting, the service water system may use fresh water or salt water as the cooling medium. Various degradation mechanisms including general corrosion, erosion/corrosion, pitting, microbiological corrosion, galvanic corrosion, under-deposit corrosion or a combination thereof continually challenge the pressure boundary structural integrity. A good source for description of corrosion degradation in cooling water systems is provided in a cited reference

  20. Development of reliability-based load and resistance factor design methods for piping

    International Nuclear Information System (INIS)

    Ayyub, Bilal M.; Hill, Ralph S. III; Balkey, Kenneth R.

    2003-01-01

    Current American Society of Mechanical Engineers (ASME) nuclear codes and standards rely primarily on deterministic and mechanistic approaches to design. The American Institute of Steel Construction and the American Concrete Institute, among other organizations, have incorporated probabilistic methodologies into their design codes. ASME nuclear codes and standards could benefit from developing a probabilistic, reliability-based, design methodology. This paper provides a plan to develop the technical basis for reliability-based, load and resistance factor design of ASME Section III, Class 2/3 piping for primary loading, i.e., pressure, deadweight and seismic. The plan provides a proof of concept in that LRFD can be used in the design of piping, and could achieve consistent reliability levels. Also, the results from future projects in this area could form the basis for code cases, and additional research for piping secondary loads. (author)

  1. Acid sphingomyelinase (Asm) deficiency patients in The Netherlands and Belgium: disease spectrum and natural course in attenuated patients.

    Science.gov (United States)

    Hollak, C E M; de Sonnaville, E S V; Cassiman, D; Linthorst, G E; Groener, J E; Morava, E; Wevers, R A; Mannens, M; Aerts, J M F G; Meersseman, W; Akkerman, E; Niezen-Koning, K E; Mulder, M F; Visser, G; Wijburg, F A; Lefeber, D; Poorthuis, B J H M

    2012-11-01

    Niemann-Pick disease (NPD) is a neurovisceral lysosomal storage disorder caused by acid sphingomyelinase (ASM) deficiency, which can be categorized as either Niemann-Pick disease type A [NPD-A], with progressive neurological disease and death in early childhood, or as Niemann-Pick disease type B [NPD-B], with a more variable spectrum of manifestations. Enzyme replacement therapy (ERT) with recombinant sphingomyelinase is currently studied as potential treatment for NPD-B patients. The objective of this study is to characterize the clinical features of patients with ASM deficiency in the Netherlands and Belgium with focus on the natural disease course of NPD-B patients. Prospective and retrospective data on ASM deficient patients were collected in The Netherlands and part of Belgium. Patients with NPD-B that could be followed prospectively were evaluated every 6-12 months for pulmonary function tests, 6 minute walk test (6 MWT), imaging (bone marrow infiltration measured by QCSI, organ volumes by MRI and CT scan of the lungs) and biochemical markers. Twenty-five patients with ASM deficiency were identified (13 males, 12 females, median age 13years, range 1-59 years). Nine patients had died at the time of the study, including four NPD-A patients at the age of 1,1, 2, 3 and five NPDB patents at the age of 5, 6, 43, 56 and 60 years. There was a high prevalence of homozygosity and compound heterozygosity for the common p.Arg608del mutation in 43% and 19% of NPD-B patients, respectively. In NPD-B patients, thrombocytopenia was present in most, while anemia and leucopenia were less common (33% and 6 % respectively). HDL cholesterol was reduced in most patients. Pulmonary disease was severe in several patients. Follow-up up to 11 years revealed a gradual decrease in platelet count. Detailed investigations in 6 NPD-B patients with follow-up in 4 patients revealed remarkable stable disease parameters up to 6 years, with some decline in pulmonary function and 6 MWT. Bone

  2. Projection of Patient Condition Code Distributions Based on Mechanism of Injury

    National Research Council Canada - National Science Library

    Zouris, James M; Walker, G. J; Blood, Christopher G

    2003-01-01

    The Medical Readiness and Strategic Plan 1998-2004 requires that the military services develop a method for linking real world patient load data with modern patient condition codes to enable planners...

  3. Evaluation procedure of the structural integrity of a pipe of nuclear use. Application of codes for design and service. Case study

    International Nuclear Information System (INIS)

    Sanzi, H.; Asta, E.

    2009-01-01

    In the present work, we are presenting the most important results of the local stresses occurred in the cracked pipes with a axial through-wall, under Failure Concept 0.1A, using Finite Element Method and Fracture Mechanics. As requested, the component has been verified based 3D FE plastic analysis, under the postulated failure loading, assuring with this method a high degree of accuracy in the results. Codes used by Design and Service, as ASME Section III Div. 1 and API 579, have been used in the analysis. (author)

  4. Sessions and Separability in Security Protocols

    DEFF Research Database (Denmark)

    Carbone, Marco; Guttman, Joshua

    2013-01-01

    Despite much work on sessions and session types in non- adversarial contexts, session-like behavior given an active adversary has not received an adequate definition and proof methods. We provide a syntactic property that guarantees that a protocol has session-respecting executions. Any uncomprom......Despite much work on sessions and session types in non- adversarial contexts, session-like behavior given an active adversary has not received an adequate definition and proof methods. We provide a syntactic property that guarantees that a protocol has session-respecting executions. Any...

  5. Multiparty Asynchronous Session Types

    DEFF Research Database (Denmark)

    Honda, Kohei; Yoshida, Nobuko; Carbone, Marco

    2016-01-01

    . This work extends the foregoing theories of binary session types to multiparty, asynchronous sessions, which often arise in practical communication-centered applications. Presented as a typed calculus for mobile processes, the theory introduces a new notion of types in which interactions involving multiple......Communication is a central elements in software development. As a potential typed foundation for structured communication-centered programming, session types have been studied over the past decade for a wide range of process calculi and programming languages, focusing on binary (two-party) sessions...... peers are directly abstracted as a global scenario. Global types retain the friendly type syntax of binary session types while specifying dependencies and capturing complex causal chains of multiparty asynchronous interactions. A global type plays the role of a shared agreement among communication peers...

  6. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  7. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  8. Performance demonstration experience for reactor pressure vessel shell ultrasonic testing

    International Nuclear Information System (INIS)

    Zado, V.

    1998-01-01

    The most ultrasonic testing techniques used by many vendors for pressurized water reactor (PWR) examinations were based on American Society of Mechanical Engineers 'Boiler and Pressurized Vessel Code' (ASME B and PV Code) Sections XI and V. The Addenda of ASME B and PV Code Section XI, Edition 1989 introduced Appendix VIII - 'Performance Demonstration for Ultrasonic Examination Systems'. In an effort to increase confidence in performance of ultrasonic testing of the operating nuclear power plants in United States, the ultrasonic testing performance demonstration examination of reactor vessel welds is performed in accordance with Performance Demonstration Initiative (PDI) program which is based on ASME Code Section XI, Appendix VIII requirements. This article provides information regarding extensive qualification preparation works performed prior EPRI guided performance demonstration exam of reactor vessel shell welds accomplished in January 1997 for the scope of Appendix VIII, Supplements IV and VI. Additionally, an overview of the procedures based on requirements of ASME Code Section XI and V in comparison to procedure prepared for Appendix VIII examination is given and discussed. The samples of ultrasonic signals obtained from artificial flaws implanted in vessel material are presented and results of ultrasonic testing are compared to actual flaw sizes. (author)

  9. Evaluation of an interactive, case-based review session in teaching medical microbiology

    Directory of Open Access Journals (Sweden)

    Kisamore Jennifer L

    2009-08-01

    Full Text Available Abstract Background Oklahoma State University-Center for Health Sciences (OSU-CHS has replaced its microbiology wet laboratory with a variety of tutorials including a case-based interactive session called Microbial Jeopardy!. The question remains whether the time spent by students and faculty in the interactive case-based tutorial is worthwhile? This study was designed to address this question by analyzing both student performance data and assessing students' perceptions regarding the tutorial. Methods Both quantitative and qualitative data were used in the current study. Part One of the study involved assessing student performance using archival records of seven case-based exam questions used in the 2004, 2005, 2006, and 2007 OSU-CHS Medical Microbiology course. Two sample t-tests for proportions were used to test for significant differences related to tutorial usage. Part Two used both quantitative and qualitative means to assess student's perceptions of the Microbial Jeopardy! session. First, a retrospective survey was administered to students who were enrolled in Medical Microbiology in 2006 or 2007. Second, responses to open-ended items from the 2008 course evaluations were reviewed for comments regarding the Microbial Jeopardy! session. Results Both student performance and student perception data support continued use of the tutorials. Quantitative and qualitative data converge to suggest that students like and learn from the interactive, case-based session. Conclusion The case-based tutorial appears to improve student performance on case-based exam questions. Additionally, students perceived the tutorial as helpful in preparing for exam questions and reviewing the course material. The time commitment for use of the case-based tutorial appears to be justified.

  10. Evaluation of an interactive, case-based review session in teaching medical microbiology

    Science.gov (United States)

    Blewett, Earl L; Kisamore, Jennifer L

    2009-01-01

    Background Oklahoma State University-Center for Health Sciences (OSU-CHS) has replaced its microbiology wet laboratory with a variety of tutorials including a case-based interactive session called Microbial Jeopardy!. The question remains whether the time spent by students and faculty in the interactive case-based tutorial is worthwhile? This study was designed to address this question by analyzing both student performance data and assessing students' perceptions regarding the tutorial. Methods Both quantitative and qualitative data were used in the current study. Part One of the study involved assessing student performance using archival records of seven case-based exam questions used in the 2004, 2005, 2006, and 2007 OSU-CHS Medical Microbiology course. Two sample t-tests for proportions were used to test for significant differences related to tutorial usage. Part Two used both quantitative and qualitative means to assess student's perceptions of the Microbial Jeopardy! session. First, a retrospective survey was administered to students who were enrolled in Medical Microbiology in 2006 or 2007. Second, responses to open-ended items from the 2008 course evaluations were reviewed for comments regarding the Microbial Jeopardy! session. Results Both student performance and student perception data support continued use of the tutorials. Quantitative and qualitative data converge to suggest that students like and learn from the interactive, case-based session. Conclusion The case-based tutorial appears to improve student performance on case-based exam questions. Additionally, students perceived the tutorial as helpful in preparing for exam questions and reviewing the course material. The time commitment for use of the case-based tutorial appears to be justified. PMID:19712473

  11. Flipped versus Traditional Classroom Information Literacy Sessions: Student Perceptions and Cognitions

    Directory of Open Access Journals (Sweden)

    Torstein Låg

    2016-12-01

    Full Text Available Teaching effectively with limited classroom time is a challenge for information literacy teachers. In the flipped classroom (FC teaching model, information transmission teaching is delivered outside of class, freeing up class time for learning activities. I adopted the FC model in sessions that were previously taught using a traditional classroom (TC model. The aim of this paper is to evaluate the FC model's relative impact on (1 student perceptions of usefulness and quality, and (2 student cognitions about the IL sessions. Responses to evaluation forms from the TC model (N = 65, were compared to those from FC model (N = 78. Students judged usefulness and quality on two 4-point rating scales. Student cognitions were elicited with an open-ended question asking for suggestions for improvement and other comments. Responses to the latter were coded by an assistant blind to the conditions. Ratings were near ceiling and similar for both conditions. Responses to the open-ended question revealed interesting trends. Students in the FC condition provided wordier comments, were more concerned with what they themselves did and could do, and with the subject matter of the session. Students in the TC condition were more concerned with how information was presented to them. Results indicate that the FC teaching model is a viable alternative for IL sessions, and that it may encourage students to engage more with IL and their own learning process.

  12. Effects of Post-Session Wheel Running on Within-Session Changes in Operant Responding

    Science.gov (United States)

    Aoyama, Kenjiro

    2007-01-01

    This study tested the effects of post-session wheel running on within-session changes in operant responding. Lever-pressing by six rats was reinforced by a food pellet under a continuous reinforcement (CRF) schedule in 30-min sessions. Two different flavored food pellets were used as reinforcers. In the wheel conditions, 30-min operant-sessions…

  13. Code of Conduct on the Safety of Research Reactors

    International Nuclear Information System (INIS)

    2006-09-01

    The Board of Governors of the International Atomic Energy Agency (IAEA) adopted the Code of Conduct on the Safety of Research Reactors on 8 March 2004. The Board's action was the culmination of several years of work to develop the Code and obtain a consensus on its provisions. The process leading to the Code began in 1998, when the International Nuclear Safety Advisory Group (INSAG) informed the Director General of concerns about the safety of research reactors. In 2000, INSAG recommended that the Secretariat begin developing an international protocol or a similar legal instrument to address those concerns. In September 2000, in resolution GC(44)/RES/14, the General Conference requested the Secretariat ''within its available resources, to continue work on exploring options to strengthen the international nuclear safety arrangements for civil research reactors, taking due account of input from INSAG and the views of other relevant bodies''. A working group convened by the Secretariat pursuant to that request recommended that ''the Agency consider establishing an international action plan for research reactors'' and that the action plan include preparation of a Code of Conduct ''that would clearly establish the desirable attributes for management of research reactor safety''. In September 2001, the Board requested that the Secretariat develop and implement, in conjunction with Member States, an international research reactor safety enhancement plan which included preparation of a Code of Conduct on the Safety of Research Reactors. Subsequently, in resolution GC(45)/RES/10.A, the General Conference endorsed the Board's request. Pursuant to that request, a Code of Conduct on the Safety of Research Reactors was drafted at two meetings of an Open-ended Working Group of Legal and Technical Experts. This draft Code of Conduct was circulated to all Member States for comment. On the basis of the responses received, a revised draft of the Code was prepared by the Secretariat

  14. Announcing the Venus Transit 2004 (VT-2004) Programme

    Science.gov (United States)

    2004-02-01

    Rare Celestial Event to be Observed by Millions Summary On June 8, 2004, Venus - the Earth's sister planet - will pass in front of the Sun. This event, a 'transit', is extremely rare - the last one occurred in 1882, 122 years ago. Easily observable in Europe, Asia, Africa and Australia, it is likely to attract the attention of millions of people on these continents and, indeed, all over the world. On this important occasion, the European Southern Observatory (ESO) has joined forces with the European Association for Astronomy Education (EAAE), the Institut de Mécanique Céleste et de Calcul des Éphémérides (IMCCE) and the Observatoire de Paris in France, as well as the Astronomical Institute of the Academy of Sciences of the Czech Republic to establish the Venus Transit 2004 (VT-2004) public education programme. It is supported by the European Commission in the framework of the European Science and Technology Week and takes advantage of this extraordinary celestial event to expose the public - in a well-considered, interactive and exciting way - to a number of fundamental issues at the crucial interface between society and basic science. VT-2004 has several components, including an instructive and comprehensive website (www.vt-2004.org). It is directed towards the wide public in general and the media, school students and their teachers, as well as amateur astronomers in particular. It invites all interested persons to participate actively in the intercontinental VT-2004 Observing Campaign (that reenacts historical Venus Transit observations) and the VT-2004 Video Contest. During the VT-2004 Final Event in November, the winners of the Video Contest will be chosen by an international jury. This meeting will also serve to discuss the project and its impact. The outcome of this rare celestial event and the overall experience from this unique public education project will clearly be of very wide interest, not just in the field of astronomy.

  15. PROGRAMME OF SEMINARS MARCH TO JUNE 2004

    CERN Multimedia

    Nathalie Dumeaux

    2004-01-01

    Situation : 09.03.2004 Dates Days Places Available* Bilingual seminars Communication Techniques-1 16, 17, 18 March 3 no Project Management 17, 18, 19 March 3 yes Introduction to Management 23, 24, 25 March 3 yes Communication Techniques-1 8, 9, 10 June 3 yes Quality Management 5, 6, 7 may 3 yes Introduction to Management - Follow-up 22, 23 June 1,5 yes Seminars in English Making Presentations 22, 23 March & 1 April 3 yes Stress Management 22, 23 April 2 yes Chairing or participating in meetings 11, 12, 13 May 3 yes *If you are interested in a seminar where there are no places available, please fill in an application form and we will contact you as soon as a new session is organised. MANAGEMENT & COMMUNICATION Nathalie Dumeaux tel. 781 44 management.communication@cern.ch

  16. Does a code make a difference – assessing the English code of practice on international recruitment

    Directory of Open Access Journals (Sweden)

    Mensah Kwadwo

    2009-04-01

    Full Text Available Abstract Background This paper draws from research completed in 2007 to assess the effect of the Department of Health, England, Code of Practice for the international recruitment of health professionals. The Department of Health in England introduced a Code of Practice for international recruitment for National Health Service employers in 2001. The Code required National Health Service employers not to actively recruit from low-income countries, unless there was government-to-government agreement. The Code was updated in 2004. Methods The paper examines trends in inflow of health professionals to the United Kingdom from other countries, using professional registration data and data on applications for work permits. The paper also provides more detailed information from two country case studies in Ghana and Kenya. Results Available data show a considerable reduction in inflow of health professionals, from the peak years up to 2002 (for nurses and 2004 (for doctors. There are multiple causes for this decline, including declining demand in the United Kingdom. In Ghana and Kenya it was found that active recruitment was perceived to have reduced significantly from the United Kingdom, but it is not clear the extent to which the Code was influential in this, or whether other factors such as a lack of vacancies in the United Kingdom explains it. Conclusion Active international recruitment of health professionals was an explicit policy intervention by the Department of Health in England, as one key element in achieving rapid staffing growth, particularly in the period 2000 to 2005, but the level of international recruitment has dropped significantly since early 2006. Regulatory and education changes in the United Kingdom in recent years have also made international entry more difficult. The potential to assess the effect of the Code in England is constrained by the limitations in available databases. This is a crucial lesson for those considering a

  17. Results from Evaluation of Proposed ASME AG-1 Section FI Metal Media Filters - 13063

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, John A.; Giffin, Paxton K.; Parsons, Michael S.; Waggoner, Charles A. [Institute for Clean Energy Technology, Mississippi State University, 205 Research Blvd Starkville, MS 39759 (United States)

    2013-07-01

    High efficiency particulate air (HEPA) filtration technology is commonly used in Department of Energy (DOE) facilities that require control of radioactive particulate matter (PM) emissions due to treatment or management of radioactive materials. Although HEPA technology typically makes use of glass fiber media, metal and ceramic media filters are also capable of filtering efficiencies beyond the required 99.97%. Sintered metal fiber filters are good candidates for use in DOE facilities due to their resistance to corrosive environments and resilience at high temperature and elevated levels of relative humidity. Their strength can protect them from high differential pressure or pressure spikes and allow for back pulse cleaning, extending filter lifetime. Use of these filters has the potential to reduce the cost of filtration in DOE facilities due to life cycle cost savings. ASME AG-1 section FI has not been approved due to a lack of protocols and performance criteria for qualifying section FI filters. The Institute for Clean Energy Technology (ICET) with the aid of the FI project team has developed a Section FI test stand and test plan capable of assisting in the qualification ASME AG-1 section FI filters. Testing done at ICET using the FI test stand evaluates resistance to rated air flow, test aerosol penetration and resistance to heated air of the section FI filters. Data collected during this testing consists of temperature, relative humidity, differential pressure, flow rate, upstream particle concentration, and downstream particle concentration. (authors)

  18. Comparison of Crack Growth Test Results at Elevated Temperature and Design Code Material Properties for Grade 91 Steel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyeong-Yeon; Kim, Woo-Gon; Kim, Nak-Hyun [Korea Atomic Energy Reserach Institute, Daejeon (Korea, Republic of)

    2015-01-15

    The material properties of crack growth models at an elevated temperature were derived from the results of numerous crack growth tests for Mod.9Cr-1Mo (ASME Grade 91) steel specimens under fatigue loading and creep loading at an elevated temperature. These crack growth models were needed for defect assessment under creep-fatigue loading. The mathematical crack growth rate models for fatigue crack growth (FCG) and creep crack growth (CCG) were determined based on the test results, and the models were compared with those of the French design code RCCMRx to investigate the conservatism of the code. The French design code RCC-MRx provides an FCG model and a CCG model for Grade 91 steel in Section III Tome 6. It was shown that the FCG model of RCC-MRx is conservative, while the CCG model is non-conservative compared with the present test data. Thus, it was shown that further validation of the property was required. Mechanical strength tests and creep tests were also conducted, and the test results were compared with those of RCC-MRx.

  19. Panel Session

    DEFF Research Database (Denmark)

    Bertelsen, Olav Wedege

    2004-01-01

    In this panel session, four researchers will discuss the role of a theoretical foundation, in particular AT, in the design of information technology based artefacts. The general discussion will take of from a specific examination of the ActAD approach.......In this panel session, four researchers will discuss the role of a theoretical foundation, in particular AT, in the design of information technology based artefacts. The general discussion will take of from a specific examination of the ActAD approach....

  20. User-inspired design methodology using Affordance Structure Matrix (ASM for construction projects

    Directory of Open Access Journals (Sweden)

    Maheswari J. Uma

    2017-01-01

    Full Text Available Traditionally, design phase of construction projects is often performed with incomplete and inaccurate user preferences. This is due to inefficiencies in the methodologies used for capturing the user requirements that can subsequently lead to inconsistencies and result in non-optimised end-result. Iterations and subsequent reworks due to such design inefficiencies is one of the major reasons for unsuccessful project delivery as they impact project performance measures such as time and cost among others. The existing design theories and practice are primarily based on functional requirements. Function-based design deals with design of artifact alone, which may yield favourable or unfavourable consequences with the design artifact. However, incorporating other interactions such as interactions between user & designer is necessary for optimised end-result. Hence, the objective of this research work is to devise a systematic design methodology considering all the three interactions among users, designers and artefacts for improved design efficiency. In this study, it has been attempted to apply the theory of affordances in a case project that involves the design of an offshore facility. A step-by-step methodology for developing Affordance Structure Matrix (ASM, which integrates House of Quality (HOQ and Design Structure Matrix (DSM, is proposed that can effectively capture the user requirements. HOQ is a popular quality management tool for capturing client requirements and DSM is a matrix-based tool that can capture the interdependency among the design entities. The proposed methodology utilises the strengths of both the tools, as DSM compliments HOQ in the process. In this methodology, different affordances such as AUA (Artifact-User-Affordance, AAA (Artifact-Artifact-Affordance and DDA (Designer-Designer-Affordance are captured systematically. Affordance is considered to be user-driven in this context that is in contrast to prevailing design

  1. Quality of recording of diabetes in the UK: how does the GP's method of coding clinical data affect incidence estimates? Cross-sectional study using the CPRD database.

    Science.gov (United States)

    Tate, A Rosemary; Dungey, Sheena; Glew, Simon; Beloff, Natalia; Williams, Rachael; Williams, Tim

    2017-01-25

    To assess the effect of coding quality on estimates of the incidence of diabetes in the UK between 1995 and 2014. A cross-sectional analysis examining diabetes coding from 1995 to 2014 and how the choice of codes (diagnosis codes vs codes which suggest diagnosis) and quality of coding affect estimated incidence. Routine primary care data from 684 practices contributing to the UK Clinical Practice Research Datalink (data contributed from Vision (INPS) practices). Incidence rates of diabetes and how they are affected by (1) GP coding and (2) excluding 'poor' quality practices with at least 10% incident patients inaccurately coded between 2004 and 2014. Incidence rates and accuracy of coding varied widely between practices and the trends differed according to selected category of code. If diagnosis codes were used, the incidence of type 2 increased sharply until 2004 (when the UK Quality Outcomes Framework was introduced), and then flattened off, until 2009, after which they decreased. If non-diagnosis codes were included, the numbers continued to increase until 2012. Although coding quality improved over time, 15% of the 666 practices that contributed data between 2004 and 2014 were labelled 'poor' quality. When these practices were dropped from the analyses, the downward trend in the incidence of type 2 after 2009 became less marked and incidence rates were higher. In contrast to some previous reports, diabetes incidence (based on diagnostic codes) appears not to have increased since 2004 in the UK. Choice of codes can make a significant difference to incidence estimates, as can quality of recording. Codes and data quality should be checked when assessing incidence rates using GP data. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

  2. Assessing play-based activities, child talk, and single session outcome in family therapy with young children.

    Science.gov (United States)

    Willis, Amber B; Walters, Lynda H; Crane, D Russell

    2014-07-01

    This exploratory, observational study was designed to reveal descriptive information regarding therapists' actual practices with preschool- and school-aged children in a single session of family therapy and to investigate change mechanisms in family play therapy that have been proposed to make this approach effective. A purposive sample of 30 families receiving family therapy was recruited and video-taped during a family session where at least one child between the ages of 4 and 12 was present. Following the session, the therapist and parent(s) completed questionnaires while one of the children (aged 4-12) was interviewed. Session recordings were coded, minute-by-minute, for participant talk time, visual aids or props used, and therapy technique type (e.g., play-based/activity vs. talk-only techniques). Hierarchical regression and canonical correlational analyses revealed evidence supporting the theory that play-based techniques promote young children's participation, enhance the quality of the child-therapist relationship, and build positive emotional experiences in family therapy. © 2013 American Association for Marriage and Family Therapy.

  3. EDF - 2004 annual results, Financial statements 2004

    International Nuclear Information System (INIS)

    Gadonneix, Pierre; Camus, Daniel

    2005-01-01

    As the world's biggest electricity generator, the EDF Group covers every sector of expertise, from generation to trading and transmission grids. EDF builds on the expertise of its people, its R and D and engineering skills, its experience as a leading industry operator and the attentive support of its customers to deliver competitive solutions that successfully reconcile economic growth with climate protection. This document presents the 2004 annual results of the Group (key figures, financial results, strategy and perspectives) as well as its Consolidated financial statements at 31 December 2004: 1. Accounting principles and methods; 2. French law of 9 August 2004 on the Public Electricity and Gas Services and Electricity and Gas Companies; 3. Significant events of 2004; 4. Changes in the scope of consolidation; 5. Information by business segment and geographical area; 6. Sales; 7. Purchases and other external expenses; 8. Average workforce; 9. Other operating income and expenses; 10. Net (increase) decrease in provisions; 11. Interest expenses; 12. Foreign exchange result; 13. Other financial income and expenses; 14. Income taxes

  4. Orifice Mass Flow Calculation in NASA's W-8 Single Stage Axial Compressor Facility

    Science.gov (United States)

    Bozak, Richard F.

    2018-01-01

    Updates to the orifice mass flow calculation for the W-8 Single Stage Axial Compressor Facility at NASA Glenn Research Center are provided to include the effect of humidity and incorporate ISO 5167. A methodology for including the effect of humidity into the inlet orifice mass flow calculation is provided. Orifice mass flow calculations provided by ASME PTC-19.5-2004, ASME MFC-3M-2004, ASME Fluid Meters, and ISO 5167 are compared for W-8's atmospheric inlet orifice plate. Differences in expansion factor and discharge coefficient given by these standards give a variation of about +/- 75% mass flow except for a few cases. A comparison of the calculations with an inlet static pressure mass flow correlation and a fan exit mass flow integration using test data from a 2017 turbofan rotor test in W-8 show good agreement between the inlet static pressure mass flow correlation, ISO 5167, and ASME Fluid Meters. While W-8's atmospheric inlet orifice plate violates the pipe diameter limit defined by each of the standards, the ISO 5167 is chosen to be the primary orifice mass flow calculation to use in the W-8 facility.

  5. Subgroup A: nuclear model codes report to the Sixteenth Meeting of the WPEC

    International Nuclear Information System (INIS)

    Talou, P.; Chadwick, M.B.; Dietrich, F.S.; Herman, M.; Kawano, T.; Konig, A.; Oblozinsky, P.

    2004-01-01

    The Subgroup A activities focus on the development of nuclear reaction models and codes, used in evaluation work for nuclear reactions from the unresolved energy region up to the pion threshold production limit, and for target nuclides from the low teens and heavier. Much of the efforts are devoted by each participant to the continuing development of their own Institution codes. Progresses in this arena are reported in detail for each code in the present document. EMPIRE-II is of public access. The release of the TALYS code has been announced for the ND2004 Conference in Santa Fe, NM, October 2004. McGNASH is still under development and is not expected to be released in the very near future. In addition, Subgroup A members have demonstrated a growing interest in working on common modeling and codes capabilities, which would significantly reduce the amount of duplicate work, help manage efficiently the growing lines of existing codes, and render codes inter-comparison much easier. A recent and important activity of the Subgroup A has therefore been to develop the framework and the first bricks of the ModLib library, which is constituted of mostly independent pieces of codes written in Fortran 90 (and above) to be used in existing and future nuclear reaction codes. Significant progresses in the development of ModLib have been made during the past year. Several physics modules have been added to the library, and a few more have been planned in detail for the coming year.

  6. Atomic power engineering under falsified safety standards

    International Nuclear Information System (INIS)

    Ackerman, A.J.

    1974-01-01

    In July 1970 the United States Department of Justice accused the American Society of Mechanical Engineers (ASME) of violating the Sherman Antitrust Act and of acting in restraint of trade by restricting the ASME Certificate of Authorization and the use of the Code Symbol Stamps to boilers and pressure vessels manufactured in the United States and Canada. During the succeeding two years attorneys for the parties in the case formulated a Consent Decree without a public confrontation in the Court. Furthermore, the membership of ASME was kept uninformed until October of 1972, after the Consent and Final Judgment had become effective and new procedures had been developed for allowing foreign manufacturers to apply the ASME Code Symbol Stamps to their products. As a consequence, a breakdown in engineered safety standards has been sanctioned and this is undermining the engineering profession's overriding reponsibility to protect the public health and safety. This breakdown of professional responsibility is especially serious in the new technology of atomic power. American insurance companies, which have traditionally written 100% insurance coverage for property damage and third party liability against explosions of high pressure steam boilers bearing the ASME Code Stamp, have refused to write such insurance coverage on nuclear reactors. In the author's opinion there is evidence that the Consent was formulated under collusive proceedings and he calls on the members and the Council of ASME to appeal for dismissal of the Consent Decree. 24 refs

  7. Gas processing in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Kovach, J.L.

    1995-02-01

    This article is a brief overview of code requirements in the nuclear air cleaning arena. NRC standards, which employ the various ASME codes, are noted. It is also noted that DOE facilities do not fall under the purview of the NRC and that DOE facilities (especially fuel cycle facilities) typically have broader gas processing activities than for power reactors. The typical differences between DOE facilities` and power reactor facilities` gas processing needs are listed, as are DOE facility components not covered by the ASME AG-1 code.

  8. SUMMARY OF GENERAL WORKING GROUP A+B+D: CODES BENCHMARKING.

    Energy Technology Data Exchange (ETDEWEB)

    WEI, J.; SHAPOSHNIKOVA, E.; ZIMMERMANN, F.; HOFMANN, I.

    2006-05-29

    Computer simulation is an indispensable tool in assisting the design, construction, and operation of accelerators. In particular, computer simulation complements analytical theories and experimental observations in understanding beam dynamics in accelerators. The ultimate function of computer simulation is to study mechanisms that limit the performance of frontier accelerators. There are four goals for the benchmarking of computer simulation codes, namely debugging, validation, comparison and verification: (1) Debugging--codes should calculate what they are supposed to calculate; (2) Validation--results generated by the codes should agree with established analytical results for specific cases; (3) Comparison--results from two sets of codes should agree with each other if the models used are the same; and (4) Verification--results from the codes should agree with experimental measurements. This is the summary of the joint session among working groups A, B, and D of the HI32006 Workshop on computer codes benchmarking.

  9. Session Types at the Mirror

    Directory of Open Access Journals (Sweden)

    Luca Padovani

    2009-12-01

    Full Text Available We (redefine session types as projections of process behaviors with respect to the communication channels they use. In this setting, we give session types a semantics based on fair testing. The outcome is a unified theory of behavioral types that shares common aspects with conversation types and that encompass features of both dyadic and multi-party session types. The point of view we provide sheds light on the nature of session types and gives us a chance to reason about them in a framework where every notion, from well-typedness to the subtyping relation between session types, is semantically -rather than syntactically- grounded.

  10. Nuclear Safety Review for the Year 2004

    International Nuclear Information System (INIS)

    2005-08-01

    In the nuclear area, challenges continue to emerge from the globalization of issues related to safety, technology, business, information, communication and security. Scientific advances and operational experience in nuclear, radiation, waste and transport technology are providing new opportunities to continuously improve safety and security by utilizing synergies between safety and security. The prime responsibility for nuclear, radiation, waste and transport safety rests with users and national governments. The Agency continues to support a Global Nuclear Safety Regime based on strong national safety infrastructures and widespread subscription to international legal instruments to maintain high levels of safety worldwide. Central to the Agency's role are the establishment of international safety standards and the provision for applying these standards, as well as the promotion of sharing information through managing the knowledge base. Nuclear power plant operational safety performance remains high throughout the world. Challenges facing the nuclear power industry include avoiding complacency, maintaining the necessary infrastructure, nuclear power plant ageing and long-term operation, as well as new reactor designs and construction. The research reactor community has a long history of safe operation. However nearly two-thirds of the world's operating research reactors are now over 30 years old and face safety and security challenges. In 2004, the Board of Governors approved the Code of Conduct on the Safety of Research Reactors to help address these challenges. In 2004, there was international consensus on radionuclide activity concentrations in materials below which regulatory controls need not apply. Key occupational radiation protection performance indicators continued to improve in 2004. Challenges include new medical practices where workers can receive high exposures, industrial radiography and worker exposure to naturally occurring radioactive material. New

  11. IDEA 2004: Section 615 (k) (Placement in Alternative Educational Setting). PHP-c111

    Science.gov (United States)

    PACER Center, 2005

    2005-01-01

    School personnel may consider any unique circumstances on a case-by-case basis when determining whether to order a change in placement for a child with a disability who violates a code of student conduct. This article describes IDEA 2004: Section 615 (k), which discusses the placement of special needs children in alternative educational settings.…

  12. Report on the FY17 Development of Computer Program for ASME Section III, Division 5, Subsection HB, Subpart B Rules

    Energy Technology Data Exchange (ETDEWEB)

    Swindeman, M. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Jetter, R. I. [Argonne National Lab. (ANL), Argonne, IL (United States); Sham, T. -L. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-01-01

    One of the objectives of the high temperature design methodology activities is to develop and validate both improvements and the basic features of ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, Division 5, High Temperature Reactors, Subsection HB, Subpart B (HBB). The overall scope of this task is to develop a computer program to aid assessment procedures of components under specified loading conditions in accordance with the elevated temperature design requirements for Division 5 Class A components. There are many features and alternative paths of varying complexity in HBB. The initial focus of this computer program is a basic path through the various options for a single reference material, 316H stainless steel. However, the computer program is being structured for eventual incorporation all of the features and permitted materials of HBB. This report will first provide a description of the overall computer program, particular challenges in developing numerical procedures for the assessment, and an overall approach to computer program development. This is followed by a more comprehensive appendix, which is the draft computer program manual for the program development. The strain limits rules have been implemented in the computer program. The evaluation of creep-fatigue damage will be implemented in future work scope.

  13. Seismic Analysis Code (SAC): Development, porting, and maintenance within a legacy code base

    Science.gov (United States)

    Savage, B.; Snoke, J. A.

    2017-12-01

    The Seismic Analysis Code (SAC) is the result of toil of many developers over almost a 40-year history. Initially a Fortran-based code, it has undergone major transitions in underlying bit size from 16 to 32, in the 1980s, and 32 to 64 in 2009; as well as a change in language from Fortran to C in the late 1990s. Maintenance of SAC, the program and its associated libraries, have tracked changes in hardware and operating systems including the advent of Linux in the early 1990, the emergence and demise of Sun/Solaris, variants of OSX processors (PowerPC and x86), and Windows (Cygwin). Traces of these systems are still visible in source code and associated comments. A major concern while improving and maintaining a routinely used, legacy code is a fear of introducing bugs or inadvertently removing favorite features of long-time users. Prior to 2004, SAC was maintained and distributed by LLNL (Lawrence Livermore National Lab). In that year, the license was transferred from LLNL to IRIS (Incorporated Research Institutions for Seismology), but the license is not open source. However, there have been thousands of downloads a year of the package, either source code or binaries for specific system. Starting in 2004, the co-authors have maintained the SAC package for IRIS. In our updates, we fixed bugs, incorporated newly introduced seismic analysis procedures (such as EVALRESP), added new, accessible features (plotting and parsing), and improved the documentation (now in HTML and PDF formats). Moreover, we have added modern software engineering practices to the development of SAC including use of recent source control systems, high-level tests, and scripted, virtualized environments for rapid testing and building. Finally, a "sac-help" listserv (administered by IRIS) was setup for SAC-related issues and is the primary avenue for users seeking advice and reporting bugs. Attempts are always made to respond to issues and bugs in a timely fashion. For the past thirty-plus years

  14. 2004 Environmental Mutagen Society Annual Meeting - Genes, Mutations and Disease: The Environmental Connection

    Energy Technology Data Exchange (ETDEWEB)

    Samson, Leona D.

    2004-08-23

    The Meeting consisted of 9 Symposia, 4 Keynote Lectures, 3 Platform Sessions and 4 Poster Sessions. In addition there were Breakfast Meetings for Special Interest Groups designed to inform attendees about the latest advances in environmental mutagenesis research. Several of the topics to be covered at this broad meeting will be of interest to the Department of Energy, Office of Science. The relevance of this meeting to the DOE derives from the fact that low dose radiation may represent one of the most significant sources of human mutations that are attributable to the environment. The EMS membership, and those who attended the EMS Annual Meeting were interested in both chemical and radiation induced biological effects, such as cell death, mutation, teratogenesis, carcinogenesis and aging. These topics thate were presented at the 2004 EMS Annual meeting that were of clear interest to DOE include: human variation in cancer susceptibility, unusual mechanisms of mutation, germ and stem cell mutagenesis, recombination and the maintenance of genomic stability, multiple roles for DNA mismatch repair, DNA helicases, mutation, cancer and aging, Genome-wide transcriptional responses to environmental change, Telomeres and genomic stability: when ends don?t meet, systems biology approach to cell phenotypic decision processes, and the surprising biology of short RNAs. Poster and platform sessions addressed topics related to environmental mutagen exposure, DNA repair, mechanisms of mutagenesis, epidemiology, genomic and proteomics and bioinformatics. These sessions were designed to give student, postdocs and more junior scientists a chance to present their work.

  15. Applying reliability centered maintenance analysis principles to inservice testing

    International Nuclear Information System (INIS)

    Flude, J.W.

    1994-01-01

    Federal regulations require nuclear power plants to use inservice test (IST) programs to ensure the operability of safety-related equipment. IST programs are based on American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements. Many of these plants also use Reliability Centered Maintenance (RCM) to optimize system maintenance. ASME Code requirements are hard to change. The process for requesting authority to use an alternate strategy is long and expensive. The difficulties of obtaining this authority make the use of RCM method on safety-related systems not cost effective. An ASME research task force on Risk Based Inservice Testing is investigating changing the Code. The change will allow plants to apply RCM methods to the problem of maintenance strategy selection for safety-related systems. The research task force is working closely with the Codes and Standards sections to develop a process related to the RCM process. Some day plants will be able to use this process to develop more efficient and safer maintenance strategies

  16. SET: Session Layer-Assisted Efficient TCP Management Architecture for 6LoWPAN with Multiple Gateways

    Directory of Open Access Journals (Sweden)

    Akbar AliHammad

    2010-01-01

    Full Text Available 6LoWPAN (IPv6 based Low-Power Personal Area Network is a protocol specification that facilitates communication of IPv6 packets on top of IEEE 802.15.4 so that Internet and wireless sensor networks can be inter-connected. This interconnection is especially required in commercial and enterprise applications of sensor networks where reliable and timely data transfers such as multiple code updates are needed from Internet nodes to sensor nodes. For this type of inbound traffic which is mostly bulk, TCP as transport layer protocol is essential, resulting in end-to-end TCP session through a default gateway. In this scenario, a single gateway tends to become the bottleneck because of non-uniform connectivity to all the sensor nodes besides being vulnerable to buffer overflow. We propose SET; a management architecture for multiple split-TCP sessions across a number of serving gateways. SET implements striping and multiple TCP session management through a shim at session layer. Through analytical modeling and ns2 simulations, we show that our proposed architecture optimizes communication for ingress bulk data transfer while providing associated load balancing services. We conclude that multiple split-TCP sessions managed in parallel across a number of gateways result in reduced latency for bulk data transfer and provide robustness against gateway failures.

  17. Summary: Hadron dynamics sessions

    International Nuclear Information System (INIS)

    Carroll, A.S.; Londergan, J.T.

    1993-01-01

    Four sessions on Hadron Dynamics were organized at this Workshop. The first topic, QCD Exclusive Reactions and Color Transparency, featured talks by Ralston, Heppelman and Strikman; the second, QCD and Inclusive Reactions had talks by Garvey, Speth and Kisslinger. The third dynamics session, Medium Modification of Elementary Interactions had contributions from Kopeliovich, Alves and Gyulassy; the fourth session Pre-QCD Dynamics and Scattering, had talks by Harris, Myhrer and Brown. An additional joint Spectroscopy/Dynamics session featured talks by Zumbro, Johnson and McClelland. These contributions are reviewed briefly in this summary. Two additional joint sessions between Dynamics and η physics are reviewed by the organizers of the Eta sessions. In such a brief review there is no way the authors can adequately summarize the details of the physics presented here. As a result, they concentrate only on brief impressionistic sketches of the physics topics discussed and their interrelations. They include no bibliography in this summary, but simply refer to the talks given in more detail in the Workshop proceedings. They focus on topics which were common to several presentations in these sessions. First, nuclear and particle descriptions of phenomena are now clearly converging, in both a qualitative and quantitative sense; they show several examples of this convergence. Second, an important issue in hadron dynamics is the extent to which elementary interactions are modified in nuclei at high energies and/or densities, and they illustrate some of these medium effects. Finally, they focus on those dynamical issues where hadron facilities can make an important, or even a unique, contribution to the knowledge of particle and nuclear physics

  18. The HITRAN 2004 molecular spectroscopic database

    Energy Technology Data Exchange (ETDEWEB)

    Rothman, L.S. [Harvard-Smithsonian Center for Astrophysics, Atomic and Molecular Physics Division, Cambridge, MA 02138 (United States)]. E-mail: lrothman@cfa.harvard.edu; Jacquemart, D. [Harvard-Smithsonian Center for Astrophysics, Atomic and Molecular Physics Division, Cambridge, MA 02138 (United States); Barbe, A. [Universite de Reims-Champagne-Ardenne, Groupe de Spectrometrie Moleculaire et Atmospherique, 51062 Reims (France)] (and others)

    2005-12-01

    This paper describes the status of the 2004 edition of the HITRAN molecular spectroscopic database. The HITRAN compilation consists of several components that serve as input for radiative transfer calculation codes: individual line parameters for the microwave through visible spectra of molecules in the gas phase; absorption cross-sections for molecules having dense spectral features, i.e., spectra in which the individual lines are unresolvable; individual line parameters and absorption cross-sections for bands in the ultra-violet; refractive indices of aerosols; tables and files of general properties associated with the database; and database management software. The line-by-line portion of the database contains spectroscopic parameters for 39 molecules including many of their isotopologues. The format of the section of the database on individual line parameters of HITRAN has undergone the most extensive enhancement in almost two decades. It now lists the Einstein A-coefficients, statistical weights of the upper and lower levels of the transitions, a better system for the representation of quantum identifications, and enhanced referencing and uncertainty codes. In addition, there is a provision for making corrections to the broadening of line transitions due to line mixing.

  19. The HITRAN 2004 molecular spectroscopic database

    International Nuclear Information System (INIS)

    Rothman, L.S.; Jacquemart, D.; Barbe, A.

    2005-01-01

    This paper describes the status of the 2004 edition of the HITRAN molecular spectroscopic database. The HITRAN compilation consists of several components that serve as input for radiative transfer calculation codes: individual line parameters for the microwave through visible spectra of molecules in the gas phase; absorption cross-sections for molecules having dense spectral features, i.e., spectra in which the individual lines are unresolvable; individual line parameters and absorption cross-sections for bands in the ultra-violet; refractive indices of aerosols; tables and files of general properties associated with the database; and database management software. The line-by-line portion of the database contains spectroscopic parameters for 39 molecules including many of their isotopologues. The format of the section of the database on individual line parameters of HITRAN has undergone the most extensive enhancement in almost two decades. It now lists the Einstein A-coefficients, statistical weights of the upper and lower levels of the transitions, a better system for the representation of quantum identifications, and enhanced referencing and uncertainty codes. In addition, there is a provision for making corrections to the broadening of line transitions due to line mixing

  20. Ranking of risk significant components for the Davis-Besse Component Cooling Water System

    International Nuclear Information System (INIS)

    Seniuk, P.J.

    1994-01-01

    Utilities that run nuclear power plants are responsible for testing pumps and valves, as specified by the American Society of Mechanical Engineers (ASME) that are required for safe shutdown, mitigating the consequences of an accident, and maintaining the plant in a safe condition. These inservice components are tested according to ASME Codes, either the earlier requirements of the ASME Boiler and Pressure Vessel Code, Section XI, or the more recent requirements of the ASME Operation and Maintenance Code, Section IST. These codes dictate test techniques and frequencies regardless of the component failure rate or significance of failure consequences. A probabilistic risk assessment or probabilistic safety assessment may be used to evaluate the component importance for inservice test (IST) risk ranking, which is a combination of failure rate and failure consequences. Resources for component testing during the normal quarterly verification test or postmaintenance test are expensive. Normal quarterly testing may cause component unavailability. Outage testing may increase outage cost with no real benefit. This paper identifies the importance ranking of risk significant components in the Davis-Besse component cooling water system. Identifying the ranking of these risk significant IST components adds technical insight for developing the appropriate test technique and test frequency