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Sample records for systems inpro manual

  1. INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Environmental Impact of Stressors. INPRO Manual

    International Nuclear Information System (INIS)

    2016-01-01

    This publication provides guidance on assessing of sustainability of a nuclear energy system (NES) in the area of environmental impact of stressors. The INPRO methodology is a comprehensive tool for the assessment of sustainability of an NES. Basic principles, user requirements and criteria have been defined in different areas of INPRO methodology. These include economics, infrastructure, waste management, proliferation resistance, environmental impact of stressors, environmental impact from depletion of resources, and safety of nuclear reactors and fuel cycle facilities. The ultimate goal of the application of the INPRO methodology is to check whether the assessed NES fulfils all the criteria, and hence the user requirements and basic principles, and therefore presents a system for a Member State that is sustainable in the long term

  2. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Physical protection. Vol. 6 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This document follows the guidelines of the INPRO report M ethodology for the assessment of innovative nuclear reactors and fuel cycles, Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) , IAEA-TECDOC-1434 (2004), together with its previous report G uidance for the evaluation for innovative nuclear reactors and fuel cycles, Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEATECDOC-1362 (2003). This INPRO manual is comprised of an overview volume and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). The INPRO Manual for the area of physical protection (Volume 6) provides guidance to the assessor of an INS (innovative nuclear energy system) under a physical protection regime in a country that is planning to install a nuclear power program (or maintaining or enlarging an existing one), and describes the application of the

  3. Guidance for the application of an assessment methodology for Innovative Nuclear Energy Systems. INPRO manual - Economics. Vol. 2 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This publication elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434 (2004), and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003) in the area of economics. The information presented in Volume 1 of the INPRO manual should be considered to be an integral part of this volume and the user should be familiar with that information. The goal of the INPRO Manual for the area of economics (Volume 2) is to provide guidance for performing an INPRO assessment, as described in Volume 1 of the INPRO manual, in the area of economics. The manual is not intended to provide guidance on how to design an INS to meet the INPRO requirements in the area of economics: rather, the focus is on the assessment method and the evaluation of the INPRO criteria in the area of economics. The INPRO assessor, i.e. the individual or group of individuals carrying out the assessment, is assumed to be knowledgeable in the area of economics and financial analysis. The INPRO assessment will either confirm that the INPRO economic criteria are fulfilled

  4. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Proliferation resistance. Vol. 5 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (laid out in this report) (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). This volume of the INPRO manual is based on the results of an INPRO study on proliferation resistance of the DUPIC fuel cycle performed by the Republic of Korea during 2005 and 2006, recommendations from IAEA consultancy meetings, and on a special service agreement with G. Pshakin (Russian Federation). The INPRO Manual starts with an introduction in Chapter 1. In Chapter 2, the necessary information is described to perform an INPRO assessment in the area of proliferation resistance. Explanatory notes on the INPRO basic principles (BP) and user requirements (UR) in the area of proliferation resistance, are reproduced in Chapter 3 to provide context for the assessor; additionally, background of each criterion (CR) and a corresponding procedure is described how to perform an INPRO assessment. The

  5. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Waste management. Vol. 4 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (laid out in this report) (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). This volume of the INPRO manual is based on the results of an INPRO study on proliferation resistance of the DUPIC fuel cycle performed by the Republic of Korea during 2005 and 2006, recommendations from IAEA consultancy meetings, and on a special service agreement with G. Pshakin (Russian Federation). The INPRO Manual starts with an introduction in Chapter 1. In Chapter 2, the necessary information is described to perform an INPRO assessment in the area of proliferation resistance. Explanatory notes on the INPRO basic principles (BP) and user requirements (UR) in the area of proliferation resistance, are reproduced in Chapter 3 to provide context for the assessor; additionally, background of each criterion (CR) and a corresponding procedure is described how to perform an INPRO assessment. The

  6. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Overview of the methodology. Vol. 1 of 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) including a CD-ROM comprising all volumes

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This document follows the guidelines of the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles, Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)', IAEA-TECDOC-1434 (2004), together with its previous report Guidance for the evaluation for innovative nuclear reactors and fuel cycles, Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEA-TECDOC-1362 (2003). This INPRO manual is comprised of an overview volume (laid out in this report), and eight additional volumes (available on a CD-ROM attached to the inside back cover of this report) covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). The overview volume sets out the philosophy of INPRO and a general discussion of the INPRO methodology. This overview volume discusses the relationship of INPRO with the UN concept of sustainability to demonstrate how the

  7. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Infrastructure. Vol. 3 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3, outlined here), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). Within INPRO, the term infrastructure can be defined as the collection of capabilities of institutions involved in a nuclear power program in a given country that are necessary for the successful deployment (or enlargement) and operation of an INS, including legal and institutional, industrial and economic, and socio-political features. Within INPRO, the definition of an INS includes activities and facilities (i.e. components) at both the front end of the fuel cycle (e.g., mining, enrichment, fuel fabrication) and the back end (e.g., reprocessing, storage, and repository) (Section 4.2.1 of Volume 1 of the INPRO manual. Consequently, within INPRO, such facilities are not considered to be a part of the INPRO area of infrastructure, albeit that they influence the size of the necessary infrastructure required in a given

  8. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Environment. Vol. 7 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (laid out in this volume) (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). This volume should provide guidance to the assessor of an INS that is planned (or maintained or enlarged), describing how to apply the INPRO methodology in the area of environment. It follows the guidelines of the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', together with its previous report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles'. The INPRO Manual starts with an introduction in Chapter 1. In Chapter 2 an overview is presented what kind of information must be available to an INPRO assessor to perform his environmental assessment. In Chapter 3 the background of the INPRO environmental basic principle BP1, the corresponding user requirements (UR) and criteria (CR) consisting of indicators (IN) and acceptance

  9. Introduction to the use of the INPRO methodology in a nuclear energy system assessment. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2010-01-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2001 on the basis of an IAEA General Conference resolution in 2000 (GC(44)/RES/21). INPRO activities have since that time been continuously endorsed by resolutions of the IAEA General Conference and by the General Assembly of the United Nations. The objectives of INPRO are to: Help ensure that nuclear energy is available to contribute, in a sustainable manner, to the goal of meeting energy needs in the 21st century; Bring together technology holders and users so that they can jointly consider the international and national actions required to ensure the sustainability of nuclear energy through innovations in technology and/or institutional arrangements. To fulfil these objectives, INPRO developed a set of basic principles, user requirements and criteria, along with an assessment method, which are the basis of the INPRO methodology for evaluation of the sustainability of innovative nuclear energy systems. To provide additional guidance in using the INPRO methodology, the nine volume INPRO Manual was developed; it consists of an overview volume and eight volumes covering the areas of economics, institutional measures (infrastructure), waste management, proliferation resistance, physical protection, environment (including the impact of stressors and the availability of resources), reactor safety, and the safety of nuclear fuel cycle facilities. To assist Member States in applying the INPRO methodology, the nuclear energy system assessment (NESA) support package is being developed. This includes a database (containing input data for assessment), provision of training courses in the INPRO methodology and examples of comprehensive assessments. This publication provides guidance on how a variety of potential users, including nuclear technology developers, experienced users and prospective first time nuclear technology users (newcomers) can apply the INPRO methodology for

  10. Lessons Learned from Nuclear Energy System Assessments (NESA) Using the INPRO Methodology. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2009-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2001 on the basis of a resolution of the IAEA General Conference in 2000 (GC(44)/RES/21). INPRO activities have since been continuously endorsed by resolutions of IAEA General Conferences and by the General Assembly of the United Nations. The objectives of INPRO are to: Help ensure that nuclear energy is available to contribute, in a sustainable manner, to meeting the energy needs of the 21st century; Bring together technology holders and users so that they can consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles. INPRO is proceeding in steps. In its first step, referred to as Phase 1, 2001 to 2006, INPRO developed a set of basic principles, user requirements and criteria together with an assessment method, which taken together, comprise the INPRO methodology for the evaluation of innovative nuclear energy systems. To provide additional guidance in using the INPRO methodology an INPRO Manual was developed; it is comprised of an overview volume and eight additional volumes covering the areas of economics, infrastructure, waste management, proliferation resistance, physical protection, environment, safety of reactors, and safety of the nuclear fuel cycle facilities. Based on a decision of the 9 INPRO steering committee in July 2006, INPRO has entered into Phase 2. This phase has three main directions of activity: methodology improvement, infrastructure/institutional aspects and collaborative projects. As of March 2009, INPRO had 28 members: Argentina, Armenia, Belarus, Belgium, Brazil, Bulgaria, Canada, Chile, China, Czech Republic, France, Germany, India, Indonesia, Japan, Republic of Korea, Morocco, Netherlands, Pakistan, the Russian Federation, Slovakia, South Africa, Spain, Switzerland, Turkey, Ukraine, United States of America and the European Commission. This IAEA-TECDOC is part of

  11. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Safety of nuclear fuel cycle facilities. Vol. 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (laid out in this report) (Volume 9).This report elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434, and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003), in the area of safety of nuclear reactors. The present version of this manual deals with safety issues related to design and operation of mining, milling, refining, conversion, enrichment, fuel fabrication, fuel storage and fuel reprocessing facilities. The INPRO Manual starts with an introduction in Chapter 1. Chapter 2 sets out the necessary input for an INPRO assessment of the safety of an innovative nuclear fuel cycle facility. This includes information on the design for the plant and the safety

  12. Status and overview of INPRO

    International Nuclear Information System (INIS)

    Moriwaki, M.; )

    2007-01-01

    INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) was initiated in the year 2000 following a resolution of the General Conference of the IAEA in order to provide a forum for discussion of experts and policy makers on all aspects of nuclear energy planning as well as on the development and deployment of innovative nuclear energy systems (INS). It brings together technology holders, users and potential users to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, and it pays particular attention to the needs of developing countries. Since its initiation, INPRO has kept growing as an international project on INS, and as of August 2006 it has 26 members including major technology holder countries and technology user and potential user countries.In July 2006, INPRO had achieved a major milestone, which is finalizing Phase 1 and starting a new stage, Phase 2 with endorsement by INPRO steering committee. Phase 1 can be characterized as INPRO methodology development stage. The INPRO methodology is a methodology to assess if a given INS can fulfil demands to be a sustainable energy option in the 21st century, in a holistic way. The INPRO methodology's holistic approach includes seven areas in its sustainability assessment: Economics, Safety, Environment, Waste Management, Proliferation Resistance, Physical Protection and Infrastructure. The demands of the methodology on INS form a hierarchy consisting of Basic Principles (BPs), User Requirements (URs) and Criteria (CR). The main achievement of Phase 1 is to define BPs, URs and CR in all seven areas (summarized as TECDOC 1434) with application tests performed by INPRO Members and create a draft manual to guide how to assess INS with INPRO methodology in a practical manner. Seven chapters of the draft manual (Overviews, Economics, Safety on nuclear power plants, Safety on fuel cycle facilities, Environment, Waste

  13. Revised INPRO Methodology in the Area of Proliferation Resistance

    International Nuclear Information System (INIS)

    Park, J.H.; Lee, Y.D.; Yang, M.S.; Kim, J.K.; Haas, E.; Depisch, F.

    2008-01-01

    The official INPRO User Manual in the area of proliferation resistance is being processed for the evaluation of innovative nuclear energy systems. Proliferation resistance is one of the goals to be satisfied for future nuclear energy systems in INPRO. The features of currently updated and released INPRO methodology were introduced on basic principles, user requirements and indicators. The criteria for an acceptance limit were specified. The DUPIC fuel cycle was evaluated based on the updated INPRO methodology for the applicability of the INPRO User Manual. However, the INPRO methodology has some difficulty in quantifying the multiplicity and robustness as well as the total cost to improve proliferation resistance. Moreover, the integration method for the evaluation results still needs to be improved.

  14. INPRO Assessment of the Planned Nuclear Energy System of Belarus. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-09-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was started in 2001 on the basis of IAEA General Conference resolution GC(44)/RES/21. INPRO activities have since been continuously endorsed by IAEA General Conference resolutions and by the General Assembly of the United Nations. The objectives of INPRO are to help ensure that nuclear energy is available to contribute, in a sustainable manner, to the goal of meeting the energy needs of the 21st century, and to bring together technology holders and users so that they can jointly consider the international and national actions required for ensuring sustainability of nuclear energy through innovations in technology and/or institutional arrangements. To fulfill these objectives, INPRO has developed a set of basic principles, user requirements and criteria, and an assessment method which, taken together, comprise the INPRO methodology for the evaluation of the long term sustainability of innovative nuclear energy systems. The INPRO methodology is documented in IAEA-TECDOC-1575 Rev.1, comprising an overview volume and eight additional volumes covering economics, institutional measures (infrastructure), waste management, proliferation resistance, physical protection, environment (impact of stressors and availability of resources), safety of reactors, and safety of nuclear fuel cycle facilities. This publication is the final report of an assessment of the planned nuclear energy system of Belarus using the INPRO methodology. The assessment was performed in 2009-2011 by Belarusian experts in a strategic partnership with the Russian Federation and with support from the IAEA's INPRO Group

  15. INPRO Assessment of the Planned Nuclear Energy System of Belarus. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-09-15

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was started in 2001 on the basis of IAEA General Conference resolution GC(44)/RES/21. INPRO activities have since been continuously endorsed by IAEA General Conference resolutions and by the General Assembly of the United Nations. The objectives of INPRO are to help ensure that nuclear energy is available to contribute, in a sustainable manner, to the goal of meeting the energy needs of the 21st century, and to bring together technology holders and users so that they can jointly consider the international and national actions required for ensuring sustainability of nuclear energy through innovations in technology and/or institutional arrangements. To fulfill these objectives, INPRO has developed a set of basic principles, user requirements and criteria, and an assessment method which, taken together, comprise the INPRO methodology for the evaluation of the long term sustainability of innovative nuclear energy systems. The INPRO methodology is documented in IAEA-TECDOC-1575 Rev.1, comprising an overview volume and eight additional volumes covering economics, institutional measures (infrastructure), waste management, proliferation resistance, physical protection, environment (impact of stressors and availability of resources), safety of reactors, and safety of nuclear fuel cycle facilities. This publication is the final report of an assessment of the planned nuclear energy system of Belarus using the INPRO methodology. The assessment was performed in 2009-2011 by Belarusian experts in a strategic partnership with the Russian Federation and with support from the IAEA's INPRO Group.

  16. INPRO Methodology to evaluate the Mexico nuclear energy system

    International Nuclear Information System (INIS)

    Cruz S, R. R.; Martin del C, C.

    2016-09-01

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  17. INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  18. A collaboration on development of requirements and guidelines for proliferation resistance of future nuclear system in the IAEA INPRO

    International Nuclear Information System (INIS)

    Oh, Keun Bae; Lee, Kwang Seok; Kim, Hyun Jun; Jeong, Ik; Yang, Myung Seung; Ko, Won Il

    2003-10-01

    This study surveyed and analyzed the existing activities and international status concerning proliferation resistance of nuclear energy systems, reviewed the features of proliferation resistance, and derived the requirements of future innovative nuclear energy systems. In IAEA INPRO, guidance for the evaluation of innovative nuclear reactors and fuel cycles on proliferation resistance was finalized through collaboration of member countries including Korea in reviewing technological status and developing the methodology for evaluation of proliferation resistance. This report, first, describes the progress of INPRO and the participation status of Korea in the project, and briefly summarizes the report of phase IA of INPRO. Next, features of proliferation resistance of nuclear systems, collaboration in the GIF and the INPRO for development of requirements and guidelines for proliferation resistance, and the final result of guidance for the evaluation of proliferation resistance were described. Finally, this study proposed measures for participation of further progress of the INPRO

  19. INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Environmental Impact from Depletion of Resources

    International Nuclear Information System (INIS)

    2015-01-01

    INPRO is an international project to help ensure that nuclear energy is available to contribute in a sustainable manner to meeting the energy needs of the 21st century. A basic principle of INPRO in the area of environmental impact from depletion of resources is that a nuclear energy system will be capable of contributing to the energy needs in the 21st century while making efficient use of non-renewable resources needed for construction, operation and decommissioning. Recognizing that a national nuclear energy programme in a given country may be based both on indigenous resources and resources purchased from abroad, this publication provides background materials and summarizes the results of international global resource availability studies that could contribute to the corresponding national assessments

  20. Enhanced defence in depth: a fundamental approach for innovative nuclear systems recommended by INPRO

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.

    2004-01-01

    In May 2001, the IAEA initiated the 'International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)'. Having in mind that nuclear power will be an important option for meeting future electricity needs, the scope of INPRO covers nuclear reactors expected to come into service in the next fifty years, together with their associated fuel cycles. This article deals with enhanced defence in depth (DID) strategy that is recommended by INPRO. This strategy is twofold: first, to prevent accidents and second, if prevention fails, to limit their potential consequences and prevent any evolution to more serious conditions. Accident prevention is the first priority. For innovative nuclear systems, the effectiveness of preventive measures should be enhanced compared with existing systems. DID is generally structured in 5 levels of protection, including successive barriers preventing the release of radioactive material to the environment. These levels are: 1) prevention of abnormal operation and failures, 2) control of abnormal operation and detection of failures, 3) control of accidents within the design basis, 4) control of severe plant conditions, including prevention and mitigation of the consequences of severe accidents, and 5) mitigation of radiological consequences of significant release of radioactive materials. In the area of nuclear safety, INPRO has set 5 principles: 1) incorporate DID as a part of the safety approach and make the 5 levels of DID more independent from each other than in current installations; 2) prevent, reduce or contain releases of radioactive or hazardous materials in any normal or abnormal plant operation; 3) incorporate increased emphasis on inherent safety characteristics and passive safety features; 4) include research and development work to bring the capability of computer codes used for the safety of innovative nuclear systems to the standard of codes used for the safety of current reactors; and 5) include a holistic life

  1. INPRO phase 1B (2nd part) joint study

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Kim, Young In; Hahn, Do Hee (and others)

    2006-08-15

    In this project, the Korean innovative nuclear energy system(INS) concept was assessed to be contributory to IAEA's INPRO Joint Study on CNFC-FR. The Korean INS concept was defined as an integrated system consisting of a sodium-cooled, metal fueled fast reactor KALIMER and a PWR(including CANDU)-KALIMER coupled closed nuclear fuel cycle for the Joint Study. From the results of the national scenario study performed based o the Korean INS concept, it has veen confirmed that the deployment of KALIMER from 2030 until 2100 could reduce the amount of domestic spent fuel from PWRs and CANDUs with no further increase in PWR spent fuel thereafter. And the amount of minor actinides disposed as high level would be decreased to zero with complete replacement of PWRs with KALIMERs. Based on the results of the national scenario study, a preliminary assessment of the Korean INS concept has been performed using the INPRO methodology and user's manuals. During the INS assessment, items requiring either improvement or complement have been detected in order to dedicate to INPRO's effort to improve the methodology. The INPRO methodology generally lack a consistency in a level of depth and quantity of evaluation criteria and parameters for six areas within the INPRO framework. It needs to complement application methods and guidances applicable to various technology levels as well as illustrations of assessment tools. In addition, it needs to develop quantification and aggregation of evaluated results, application of weighting factor methods, and a synthetic manual for integrated assessment procedure and methodology.

  2. INPRO phase 1B (2nd part) joint study

    International Nuclear Information System (INIS)

    Lee, Yong Bum; Kim, Young In; Hahn, Do Hee

    2006-08-01

    In this project, the Korean innovative nuclear energy system(INS) concept was assessed to be contributory to IAEA's INPRO Joint Study on CNFC-FR. The Korean INS concept was defined as an integrated system consisting of a sodium-cooled, metal fueled fast reactor KALIMER and a PWR(including CANDU)-KALIMER coupled closed nuclear fuel cycle for the Joint Study. From the results of the national scenario study performed based o the Korean INS concept, it has veen confirmed that the deployment of KALIMER from 2030 until 2100 could reduce the amount of domestic spent fuel from PWRs and CANDUs with no further increase in PWR spent fuel thereafter. And the amount of minor actinides disposed as high level would be decreased to zero with complete replacement of PWRs with KALIMERs. Based on the results of the national scenario study, a preliminary assessment of the Korean INS concept has been performed using the INPRO methodology and user's manuals. During the INS assessment, items requiring either improvement or complement have been detected in order to dedicate to INPRO's effort to improve the methodology. The INPRO methodology generally lack a consistency in a level of depth and quantity of evaluation criteria and parameters for six areas within the INPRO framework. It needs to complement application methods and guidances applicable to various technology levels as well as illustrations of assessment tools. In addition, it needs to develop quantification and aggregation of evaluated results, application of weighting factor methods, and a synthetic manual for integrated assessment procedure and methodology

  3. Main messages of INPRO

    International Nuclear Information System (INIS)

    Khoroshev, M.

    2004-01-01

    In this presentation author deals with activities of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). It is concluded that INPRO has political, financial and technical support from Member States; Phase IA on the establishment of basic principles user requirements and criteria the development of an assessment methodology has been finalised; Phase IB addresses the validation of the INPRO methodology and the assessment of concepts and approaches; INPRO is open to all interested Member States an international organisations

  4. CAREM X INPRO case study

    International Nuclear Information System (INIS)

    Florido, P.C.; Brasnarof, D.; Delmastro, D.; Azpitarte, O.E.

    2004-01-01

    In order to assess and compare the performance of innovative nuclear energy systems INPRO has defined a set of basic principles, user requirements and criteria to be met in different areas (economics, sustainability and environment, safety, waste management and proliferation). This paper illustrates the use of INPRO methodology to a particular reactor system. Argentina is performing CAREM X Nuclear System Case Study based on CAREM nuclear reactor and Once Through Fuel Cycle, using SIGMA for enriched uranium production, and a deep geological repository for final disposal of high level waste after surface intermediate storage in horizontal natural convection silos, to verify INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) methodology. 6 aspects have been considered: 1) enrichment based on Sigma enrichment plant (gas diffusion technology), 2) conversion to UO 2 , 3) fuel manufacturing, 4) CAREM-300 based reactor technology, 5) intermediate spent fuel storage, and 6) deep geological repository of spent fuels. Projections show that developing countries could play a crucial role in the deployment of nuclear energy, in the next fifty years. This case study will be highly useful for checking INPRO methodology for this scenario. In this paper, the preliminary findings of the Case Study are presented, including proposals to improve the INPRO methodology

  5. INPRO-SYNERGIES - a new international INPRO/IAEA project

    International Nuclear Information System (INIS)

    Andreeva-Andrievskaya, L.N.; Kuznetsov, V.V.; Busurin, Yu.N.; Ponomarev, A.V.; )

    2012-01-01

    The new INPRO project entitled Synergistic Nuclear Energy Regional Group Interactions Evaluated for Sustainability (INPRO- SYNERGIES) is described. The project aims to improve the analytical software and databases to model more specifically the particular forms of synergistic architectures involving collaboration among supplier countries and user countries to support an efficient transition towards sustainable energy systems. The project's objectives, methods and contents of the work are analyzed. The synergistic collaborative scenarios for fuel cycle infrastructure development are evaluated. The course of the project and expected outputs are also described [ru

  6. International project on innovative nuclear reactors and fuel cycles (INPRO)

    International Nuclear Information System (INIS)

    Omoto, A.

    2006-01-01

    The IAEA's project INPRO was initiated in order to provide a forum for discussion of experts and policy makers on all aspects of nuclear energy planning as well as on the development and deployment of innovative nuclear energy systems (INS). It brings together technology holders users and potential users to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, but it pays particular attention to the needs of developing countries. Currently INPRO members count 24 including even three countries, which are not yet operating nuclear reactors. Its initial phase has produced an outlook into the future of the energy markets and defined basic principles, user requirements and criteria in the following areas as TECDOC1362 in June 2003; Economics, Environment, Fuel Cycle and Waste, Safety, Proliferation Resistance and Crosscutting Issues. This assessment methodology can be applied for screening an INS, comparing different INS to find a preferred INS consistent with the needs of a given state, and identifying RD and D needs. The methodology has be validated through case studies and updated as TECDOC1434 in December 2004. Currently, besides producing a manual for each chapter of TECDOC1434, six assessment studies of various INS options are being carried out and the number of such studies is increasing. Further several tasks are ongoing including modeling and analysis of global and regional balance of resources and INS deployment scenarios in order to gain the better perspective of future implication of INS deployment as well as to identify challenges and opportunities of INS. It is envisioned that INPRO will continue to develop with three planned major pillars of activity; methodology, infrastructure and coordination for planning of R and D activities. The paper discusses the progress and status of INPRO as well as the future prospect of INPRO activities

  7. INPRO – Networking Practices and Opportunities

    International Nuclear Information System (INIS)

    Grigoriev, Alexey; Kazennov, Alexey

    2013-01-01

    INPRO cooperates with Member States to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. To bring together – i.e. to network - technology holders and users so that they can jointly consider international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles. INPRO is part of the integrated services of the IAEA provided to Member States considering initial development or expansion of nuclear energy programmes. INPRO is an effective mechanisms for networking, and for growing new generations of researchers and managers ultimately required for the development and deployment of innovative sustainable nuclear energy systems

  8. Approaches for the Assessment of the Innovative Nuclear System of Ukraine on the Base of INPRO Methodology

    International Nuclear Information System (INIS)

    Afanas'ev, A.A.; Vlasenko, N.I.

    2007-01-01

    Approaches for the preliminary and comparative assessment of Innovative Nuclear System (INS) of Ukraine using INPRO methodology (IAEA TECDOC-1434) suggested for the period up to 2030, which must answer the comprehensive purpose of sustainable development, contribute to strengthening of the non-proliferation principles and solving an energy problems supply on national and regional levels are presented in the paper. Using assessment results of the INS based on evolutionary designs will allow Ukraine to build informative, methodological and technical basis for choice of the INS based on innovative design which could be offered for deployment in Ukraine after 1030

  9. Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

    2007-11-15

    Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR.

  10. Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

    International Nuclear Information System (INIS)

    Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

    2007-11-01

    Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR

  11. Overview of the INPRO Project

    Energy Technology Data Exchange (ETDEWEB)

    Kupitz, J.; Depisch, F.; Zou, Y.

    2004-10-03

    During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also the requirements for the way the energy will be supplied. Within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, an inventory of requirements for the future of nuclear energy systems has been collected as well a methodology developed by INPRO to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also the infrastructure, technical as well as institutional has to be adjusted to the anticipated changes in the world such as the globalization. As a contribution to the conference the main messages of INPRO will be presented.

  12. Overview of the INPRO project

    International Nuclear Information System (INIS)

    Kupitz, J.; Depisch, F.

    2004-01-01

    During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also the requirements for the way the energy will be supplied. Within INPRO the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, an inventory of requirements for the future of nuclear energy systems has been collected as well a methodology developed by INPRO to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also the infrastructure, technical as well institutional has to be adjusted to the anticipated changes in the world such as the globalization. As a contribution to the conference the main messages of INPRO will be presented

  13. Overview of the INPRO Project

    International Nuclear Information System (INIS)

    Kupitz, J.; Depisch, F.; Zou, Y.

    2004-01-01

    During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also the requirements for the way the energy will be supplied. Within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, an inventory of requirements for the future of nuclear energy systems has been collected as well a methodology developed by INPRO to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also the infrastructure, technical as well as institutional has to be adjusted to the anticipated changes in the world such as the globalization. As a contribution to the conference the main messages of INPRO will be presented

  14. A collaboration on extended INPRO case study of the DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Yang, M. S.; Ko, W. I. (and others)

    2007-05-15

    Since 1992, KAERI, AECL, United States Department of States(USDOS) and IAEA have performed the DUPIC fuel cycle development activities as an international cooperative research program, which has now been chosen as a target nuclear system for an INPRO case study. This study will focus on a further improvement and modification of the basic principles, user requirements and acceptance limits, which are defined in the IAEA-TECDOC-1434 for an evaluation of its proliferation-resistance through a proliferation-resistance assessment of the whole fuel cycle of DUPIC based on the INPRO methodology. In order to further develop an evaluation method for a proliferation-resistance based on the INPRO methodology, the basic principles, user requirements and acceptance limits of a proliferation-resistance was reviewed and quantified. Then the evaluation model (material flow, facility scale, reference fuel, etc.) of the DUPIC fuel cycle was developed and a proliferation-resistance assessment of the DUPIC fuel cycle including the PWR fuel cycle was performed by using the revised INPRO methodology in the area of a proliferation resistance. Also, the recommendations for a further improvement of INPRO methodology were suggested through examining the INPRO methodology for a proliferation resistance assessment. Through the proliferation resistance assessment of the whole fuel cycle of DUPIC including the PWR fuel cycle, the proliferation-resistance methodology was updated and re-established. And based on its experience, The research results can be used not only to evaluate and determine the future domestic proliferation-resistant fuel cycles which were derived from the GEN{sub I}V or INPRO programs but also to improve a system design to enhance its proliferation resistance. The present results will be utilized for the development of an INPRO User's Manual which is being developed as an important issue by IAEA. The credibility of the research results were ensured by the IAEA

  15. A collaboration on extended INPRO case study of the DUPIC fuel cycle

    International Nuclear Information System (INIS)

    Park, J. H.; Yang, M. S.; Ko, W. I.

    2007-05-01

    Since 1992, KAERI, AECL, United States Department of States(USDOS) and IAEA have performed the DUPIC fuel cycle development activities as an international cooperative research program, which has now been chosen as a target nuclear system for an INPRO case study. This study will focus on a further improvement and modification of the basic principles, user requirements and acceptance limits, which are defined in the IAEA-TECDOC-1434 for an evaluation of its proliferation-resistance through a proliferation-resistance assessment of the whole fuel cycle of DUPIC based on the INPRO methodology. In order to further develop an evaluation method for a proliferation-resistance based on the INPRO methodology, the basic principles, user requirements and acceptance limits of a proliferation-resistance was reviewed and quantified. Then the evaluation model (material flow, facility scale, reference fuel, etc.) of the DUPIC fuel cycle was developed and a proliferation-resistance assessment of the DUPIC fuel cycle including the PWR fuel cycle was performed by using the revised INPRO methodology in the area of a proliferation resistance. Also, the recommendations for a further improvement of INPRO methodology were suggested through examining the INPRO methodology for a proliferation resistance assessment. Through the proliferation resistance assessment of the whole fuel cycle of DUPIC including the PWR fuel cycle, the proliferation-resistance methodology was updated and re-established. And based on its experience, The research results can be used not only to evaluate and determine the future domestic proliferation-resistant fuel cycles which were derived from the GEN I V or INPRO programs but also to improve a system design to enhance its proliferation resistance. The present results will be utilized for the development of an INPRO User's Manual which is being developed as an important issue by IAEA. The credibility of the research results were ensured by the IAEA Consultant

  16. Framework for Assessing Dynamic Nuclear Energy Systems for Sustainability: Final Report of the INPRO Collaborative Project GAINS

    International Nuclear Information System (INIS)

    2013-01-01

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. As an integral part of Phase 2 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), several collaborative projects (CPs) were established by INPRO members. The CP, 'Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle (GAINS)', was one of them. This CP was jointly implemented in 2008-2011 by Belgium, Canada, China, the Czech Republic, France, India, Italy, Japan, the Republic of Korea, the Russian Federation, Slovakia, Ukraine, the United States of America and the European Commission

  17. Evaluation of proliferation resistance using the INPRO methodology

    International Nuclear Information System (INIS)

    Yang, Myung Seung; Park, Joo Hwan; Ko, Won Il; Song, Kee Chan; Choi, Kun Mo; Kim, Jin Kyoung

    2007-01-01

    The IAEA launched the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and developed the INPRO Methodology to provide guidelines and to assess the characteristics of a future innovative nuclear energy system in areas such as safety, economics, waste management, and proliferation resistance. The proliferation resistance area of the INPRO Methodology is reviewed here, and modifications for further improvements are proposed. The evaluation metrics including the evaluation parameters, evaluation scales and acceptance limits are developed for a practical application of the methodology to assess the proliferation resistance. The proliferation resistant characteristics of the DUPIC fuel cycle are assessed by applying the modified INPRO Methodology based on the developed evaluation metrics and acceptance criteria. The evaluation procedure and the metrics can be utilized as a reference for an evaluation of the proliferation resistance of a future innovative nuclear energy system

  18. Assessment of Nuclear Energy Systems Based on a Closed Nuclear Fuel Cycle with Fast Reactors. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2010-01-01

    A Joint Study was started in 2005 and completed in 2007 within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Canada, China, France, India, Japan, the Republic of Korea, the Russian Federation, and Ukraine participated in this study. The objectives were to assess a nuclear energy system based on a closed fuel cycle (CNFC) with fast reactors (FR) regarding its sustainability, determine milestones for the nuclear energy system deployment, and establish frameworks for, and areas of, collaborative R and D work. The assessment was carried out in accordance with the requirements of INPRO methodology and guiding documents of the Joint Study developed and approved by the participating parties (Canada and Ukraine participated in the discussions during the Joint Study, but did not contribute to the assessments themselves). The Joint Study was implemented in steps. In its first step, nominated experts, during the course of extensive discussions, analyzed the country/region/world context data; discussed national and global scenarios of introduction of the CNFC-FR systems; identified technologies suitable for the INS; and arrived at a broad definition of a common CNFC-FR system. In the second step, the participants of the study examined characteristics of CNFC-FR systems for compliance with criteria of sustainability developed in the INPRO methodology in the area of economics, safety, environment, waste management, proliferation resistance, and infrastructure. The results of the study were submitted to and endorsed by the INPRO Steering Committee in meetings held in Vienna 2005 - 2007. The authors of the Joint Study report highly appreciate the valuable comments provided by delegates of the INPRO Steering Committee meetings as well as the advice and assistance of the other experts. Due to the length of the Joint Study report, a summary of the results was produced, which is the content of this publication. The full text of the Joint Study

  19. Romanian perspective on IAEA-INPRO initiative

    International Nuclear Information System (INIS)

    Banches, E.; Constantin, M.; Nicolae, R.

    2009-01-01

    INPRO objectives and status of the IAEA project started in 2001 and concerns the deployment of Innovative Nuclear Systems (INS) in 21st century, as solution to sustainable power development. The last achievements and the new INPRO Steering Committee directions established for 2010-2011 period, are presented. A balanced analysis of needs, resources and expectations, justifies the Romanian Statement at the 14th Steering Committee Meeting (SCM), and participant as an observer in three Collaborative Projects, in Common User Considerations (CUC) by Developing Countries for Future NPP and in SCM. The feedback of the last participatory actions in the project, justifies the Nuclear Agency recommendations for Nuclear National Program (PNN) adjustments: first, the need to apply INPRO methodology in a new national study regarding INS perspective and opportunity in Romania to use CANDU NPPs for LWRs fuel closing cycle at international level; secondly, the need to improve commitment of policy makers in forecasting financial INS support; and thirdly, to sustain the European legislation and international and national arrangements in order to facilitate nuclear regional services. (authors)

  20. Assessment of Nuclear Energy Systems based on a Closed Nuclear Fuel Cycle with Fast Reactors. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2012-09-01

    A Joint Study was started in 2005 and completed in 2007 within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Canada, China, France, India, Japan, the Republic of Korea, the Russian Federation, and Ukraine participated in this study. The objectives were to assess a nuclear energy system based on a closed fuel cycle (CNFC) with fast reactors (FR) regarding its sustainability, determine milestones for the nuclear energy system deployment, and establish frameworks for, and areas of, collaborative R and D work. The assessment was carried out in accordance with requirements of INPRO methodology and guiding documents of the Joint Study developed and approved by the participating parties (Canada and Ukraine participated in the discussions during the Joint Study but did not contribute to the assessments themselves). The Joint Study was implemented in steps. In its first step, nominated experts in course of extensive discussions analyzed the country/region/world context data, discussed national and global scenarios of introduction of the INS CNFC-FR, identified technologies suitable for the INS, and arrived at a broad definition of a common INS CNFC-FR. In the second step, the participants of the study examined characteristics of INS CNFC-FR for compliance with criteria of sustainability developed in the INPRO methodology in the domain of economics, safety, environment, waste management, proliferation resistance, physical protection and infrastructure. The results of the study were submitted to and endorsed by the INPRO Steering Committee meetings held in Vienna 2005-2007. The authors of the report highly appreciate the valuable comments provided by delegates of INPRO Steering Committee meetings as well as the advice and assistance of the other experts. Due to the length of the Joint Study report a summary of the results was produced, which was published as a hard copy. The full text of the Joint Study report is available on the CD

  1. INPRO results and future tasks. A look from Russia

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Velikhov, E.P.; Kuznetsov, V.P.; Zrodnikov, A.V.; Bolshov, L.A.

    2004-01-01

    Russia is supporting the INPRO Innovative Project, being driven by the IAEA in the field of innovative nuclear energy. The participation of Russia in the INPRO is a part of the realization process of Russia's President Initiative, presented at the United Nations Millennium Summit in September 2000, on the creation of a new generation of nuclear energy systems, meeting the requirements of sustainable development and excluding using the nuclear weapons technologies and materials. In 2003 the draft INPRO Methodology for assessment of the innovative nuclear energy systems correspondence to the requirements of sustainable development has been developed. At present time the Methodology's approbation on the examples of national nuclear power technologies is being completed. It is supposed that the Methodology will be used as a navigator for the world nuclear energy development process. The INPRO stresses the timeliness of nuclear energy development problems. The International Organization on nuclear fuel cycle is the key decision of non-proliferation problem. Important are the questions of interaction and particularities of the INPRO and Generation IV programs. State support and international cooperation are conditions for effective development of nuclear energy. (authors)

  2. INPRO: status, ongoing, activities and outlook

    International Nuclear Information System (INIS)

    Khoroshev, M.

    2004-01-01

    In this presentation author deals with activities of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Presentation const of the following chapters: Introduction; Goals of INPRO and results of Phase IA; Basic principles, user requirements and methodology for assessment of INS; Highlights of INPRO in the areas of economics, environment, safety, waste management, proliferation resistance and infrastructure; Outlook Phase II of INPRO. It is concluded that INPRO has political, financial and technical support from Member States; Phase IA on the establishment of basic principles user requirements and criteria the development of an assessment methodology has been finalised; Phase IB addresses the validation of the INPRO methodology and the assessment of concepts and approaches; INPRO is open to all interested Member States an international organisations

  3. Establishment of Assessment Methodology Improvement of IAEA INPRO Proliferation Resistance

    International Nuclear Information System (INIS)

    Park, J. H.; Yang, M. S.; Song, K. C.; Ko, W. I.; Kim, H. D.; Kim, Y. I.; Rhee, B. W.; Kim, H. T.

    2008-03-01

    For the development of assessment methodology of acquisition and diversion pathway of nuclear material, the PR assessment methodology which has been developed by GEN-IV PR and PP group was reviewed regarding the acquisition and diversion pathway of nuclear material and we proposed the research areas to develop the model of acquisition and diversion pathway of nuclear material including misuse of fuel cycle facilities and one of the IAEA INPRO CRPs which is aiming to develop its model. From the present study, its preliminary model for acquisition and diversion pathway of nuclear material was obtained. For preliminary evaluation of DUPIC system using methodology of acquisition/diversion pathway of nm and review of pyro-processing system characteristics, the research direction and work procedure was established to develop the assessment methodology of User Requirement 4 of INPRO PR by; 1) selection of the possible pathway to acquire and divert the nuclear material of DUPIC system, 2) the analysis of selected pathway, 3) the development of the assessment methodology of robustness and multiplicity of an INS. And, the PR characteristics and process/material flow analysis of the Pyro-processing system were preliminarily studied. For establishment of R and D direction for an INS and supporting international cooperation research, the collaborative research project titled as 'Acquisition and Diversion pathway analysis of Proliferation Resistance' as one of activities of IAEA INPRO was proposed, since Korean Government decided to actively support the IAEA INPRO. In order to review and clarify the Terms of Reference (TOR) of a Korean Proposed Collaborative Project (ROK1), two INPRO Consultancy Meetings were held. Its results were presented at two INPRO Steering Committees and the finalized TOR of Korean Proposal submit the 12-th INPRO Steering Committee Meeting which was held Dec. 3-5 2007. Four participants including USA, Canada, China and European Community (EC) have decided

  4. Establishment of Assessment Methodology Improvement of IAEA INPRO Proliferation Resistance

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Yang, M. S.; Song, K. C.; Ko, W. I.; Kim, H. D.; Kim, Y. I.; Rhee, B. W.; Kim, H. T.

    2008-03-15

    For the development of assessment methodology of acquisition and diversion pathway of nuclear material, the PR assessment methodology which has been developed by GEN-IV PR and PP group was reviewed regarding the acquisition and diversion pathway of nuclear material and we proposed the research areas to develop the model of acquisition and diversion pathway of nuclear material including misuse of fuel cycle facilities and one of the IAEA INPRO CRPs which is aiming to develop its model. From the present study, its preliminary model for acquisition and diversion pathway of nuclear material was obtained. For preliminary evaluation of DUPIC system using methodology of acquisition/diversion pathway of nm and review of pyro-processing system characteristics, the research direction and work procedure was established to develop the assessment methodology of User Requirement 4 of INPRO PR by; 1) selection of the possible pathway to acquire and divert the nuclear material of DUPIC system, 2) the analysis of selected pathway, 3) the development of the assessment methodology of robustness and multiplicity of an INS. And, the PR characteristics and process/material flow analysis of the Pyro-processing system were preliminarily studied. For establishment of R and D direction for an INS and supporting international cooperation research, the collaborative research project titled as 'Acquisition and Diversion pathway analysis of Proliferation Resistance' as one of activities of IAEA INPRO was proposed, since Korean Government decided to actively support the IAEA INPRO. In order to review and clarify the Terms of Reference (TOR) of a Korean Proposed Collaborative Project (ROK1), two INPRO Consultancy Meetings were held. Its results were presented at two INPRO Steering Committees and the finalized TOR of Korean Proposal submit the 12-th INPRO Steering Committee Meeting which was held Dec. 3-5 2007. Four participants including USA, Canada, China and European Community (EC

  5. Program Management System manual

    International Nuclear Information System (INIS)

    1986-01-01

    The Program Management System (PMS), as detailed in this manual, consists of all the plans, policies, procedure, systems, and processes that, taken together, serve as a mechanism for managing the various subprograms and program elements in a cohesive, cost-effective manner. The PMS is consistent with the requirements of the Nuclear Waste Policy Act of 1982 and the ''Mission Plan for the Civilian Radioactive Waste Management Program'' (DOE/RW-0005). It is based on, but goes beyond, the Department of Energy (DOE) management policies and procedures applicable to all DOE programs by adapting these directives to the specific needs of the Civilian Radioactive Waste Management program. This PMS Manual describes the hierarchy of plans required to develop and maintain the cost, schedule, and technical baselines at the various organizational levels of the Civilian Radioactive Waste Management Program. It also establishes the management policies and procedures used in the implementation of the Program. These include requirements for internal reports, data, and other information; systems engineering management; regulatory compliance; safety; quality assurance; and institutional affairs. Although expanded versions of many of these plans, policies, and procedures are found in separate documents, they are an integral part of this manual. The PMS provides the basis for the effective management that is needed to ensure that the Civilian Radioactive Waste Management Program fulfills the mandate of the Nuclear Waste Policy Act of 1982. 5 figs., 2 tabs

  6. The international project on innovative nuclear reactors and fuel cycles (INPRO) - status and trends

    International Nuclear Information System (INIS)

    Gowin, Peter J.; Beatty, Randy L.

    2010-01-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2000. As of April 2010, INPRO has 31 members and is implementing activities in five programme areas: A: Nuclear Energy System Assessments (NESA) using the INPRO Methodology Assisting Member States in performing Nuclear Energy System Assessments (NESA) using the INPRO methodology, in support of long-term strategic planning and nuclear energy deployment decision making. B: Global Vision Developing global and regional nuclear energy scenarios, on the basis of a scientific-technical pathway analysis, that lead to a global vision on sustainable nuclear energy development in the 21. century, and supporting Member States in working towards that vision. C: Innovations in Nuclear Technology Fostering collaboration among INPRO Member States on selected innovative nuclear technologies and related R and D that contribute to sustainable nuclear energy. D: Innovations in Institutional Arrangements Investigating and fostering collaboration on innovative institutional and legal arrangements for the use of innovative nuclear systems in the 21. century and supporting Member States in developing and implementing such innovative arrangements. E: INPRO Dialogue Forum Bringing together technology holders and technology users to discuss, debate and share information on desirable innovations, both technical and institutional, but also national long-term nuclear planning strategies and approaches and, on the highest level, the global nuclear energy system. The paper presents main INPRO achievements to date, the current status of activities in these five programme areas and recent INPRO publications, in particular in support of nuclear energy system assessments (NESA) using the INPRO methodology. (authors)

  7. Passive Safety Systems in Advanced Water Cooled Reactors (AWCRS). Case Studies. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-09-01

    This report presents the results from the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) collaborative project (CP) on Advanced Water Cooled Reactor Case Studies in Support of Passive Safety Systems (AWCR), undertaken under the INPRO Programme Area C. INPRO was launched in 2000 - on the basis of a resolution of the IAEA General Conference (GC(44)/RES/21) - to ensure that nuclear energy is available in the 21st century in a sustainable manner, and it seeks to bring together all interested Member States to consider actions to achieve innovation. An important objective of nuclear energy system assessments is to identify 'gaps' in the various technologies and corresponding research and development (R and D) needs. This programme area fosters collaboration among INPRO Member States on selected innovative nuclear technologies to bridge technology gaps. Public concern about nuclear reactor safety has increased after the Fukushima Daiichi nuclear power plant accident caused by the loss of power to pump water for removing residual heat in the core. As a consequence, there has been an increasing interest in designing safety systems for new and advanced reactors that are passive in nature. Compared to active systems, passive safety features do not require operator intervention, active controls, or an external energy source. Passive systems rely only on physical phenomena such as natural circulation, thermal convection, gravity and self-pressurization. Passive safety features, therefore, are increasingly recognized as an essential component of the next-generation advanced reactors. A high level of safety and improved competitiveness are common goals for designing advanced nuclear power plants. Many of these systems incorporate several passive design concepts aimed at improving safety and reliability. The advantages of passive safety systems include simplicity, and avoidance of human intervention, external power or signals. For these reasons, most

  8. Analysis of Russian transition scenarios to innovative nuclear energy system based on thermal and fast reactors with closed nuclear fuel cycle using INPRO methodology

    International Nuclear Information System (INIS)

    Kagramanyan, V.S.; Poplavskaya, E.V.; Korobeynikov, V.V.; Kalashnikov, A.G.; Moseev, A.L.; Korobitsyn, V.E.; Andreeva-Andrievskaya, L.N.

    2011-01-01

    This paper presents the results of the analysis of modeling of Russian nuclear energy (NE) scenarios on the basis of thermal and fast reactors with closed nuclear fuel cycle (NFC). Modeling has been carried out with use of CYCLE code (SSC RF IPPE's tool) designed for analysis of Nuclear Energy System (NES) with closed NFC taking into account plutonium and minor actinides (MA) isotopic composition change during multi-recycling of fuel in fast reactors. When considering fast reactor introduction scenarios, one of important questions is to define optimal time for their introduction and related NFC's facilities. Analysis of the results obtained has been fulfilled using the key INPRO indicators for sustainable energy development. It was shown that a delay in fast reactor introduction led to serious ecological, social and finally economic risks for providing energy security and sustainable development of Russia in long-term prospects and loss of knowledge and experience in mastering innovative technologies of fast reactors and related nuclear fuel cycle. (author)

  9. IAEA activities in the development of innovative nuclear technology – the Role of INPRO

    International Nuclear Information System (INIS)

    Drace, Z.

    2013-01-01

    INPRO provides for: • Development of global and regional nuclear energy evolution scenarios and visions to inform national policy development and collaboration among Member States; • Improved understanding of practical steps in transitions to regionally and globally sustainable NESs; • Improved understanding of innovations in technical and institutional features of NES that support transition to sustainable NES; • Holistic assessment of proposed and planned NES to assure that the stated objective of sustainability is rigorously measureable using a defensible consensus approach; and • Communication of insights gained through INPRO activities, and other subjects of direct shared interest to sustainable nuclear energy development, to all involved and interested stakeholders through the INPRO Dialogue Forum. All INPRO activities combined seek to develop a structured holistic approach to assessment and dynamic analysis of NES sustainability. This, together with consideration of both innovative technology and institutional arrangements, may potentially lead to improved understanding of the approach to globally sustainable nuclear energy systems

  10. Program management system manual

    International Nuclear Information System (INIS)

    1989-08-01

    OCRWM has developed a program management system (PMS) to assist in organizing, planning, directing and controlling the Civilian Radioactive Waste Management Program. A well defined management system is necessary because: (1) the Program is a complex technical undertaking with a large number of participants, (2) the disposal and storage facilities to be developed by the Program must be licensed by the Nuclear Regulatory Commission (NRC) and hence are subject to rigorous quality assurance (QA) requirements, (3) the legislation mandating the Program creates a dichotomy between demanding schedules of performance and a requirement for close and continuous consultation and cooperation with external entities, (4) the various elements of the Program must be managed as parts of an integrated waste management system, (5) the Program has an estimated total system life cycle cost of over $30 billion, and (6) the Program has a unique fiduciary responsibility to the owners and generators of the nuclear waste for controlling costs and minimizing the user fees paid into the Nuclear Waste Fund. This PMS Manual is designed and structured to facilitate strong, effective Program management by providing policies and requirements for organizing, planning, directing and controlling the major Program functions

  11. The IAEA international project on innovative nuclear reactors and fuel cycles (INPRO): current and future activities

    International Nuclear Information System (INIS)

    Kupitz, J.; Depisch, F.; Kuznetsov, V.

    2004-01-01

    Upon resolutions of the IAEA General Conference in 2000, the IAEA initiated International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). The objective of INPRO, which comprises two phases, is to support sustainable deployment and use of nuclear technology to meet the global energy needs in the next 50 years and beyond. During Phase I, work is subdivided into two sub phases. Phase 1A focused on determining user requirements in the areas of economics, environment, safety, proliferation resistance, and recommendations in the area of so-called crosscutting issues, which are legal, institutional, and infrastructure issues accompanying the deployment of nuclear power, and is targeted at developing a methodology and guidelines for the assessment of various nuclear reactor and fuel cycle concepts and approaches. Phase 1A was finalised in June 2003 with its results now available as IAEA TECDOC-1362. Phase 1B has started in July 2003. During this phase interested Member States are performing case studies to validate the INPRO methodology and, later on, to assess selected innovative nuclear energy systems using the updated INPRO methodology. In accordance with the INPRO Terms of Reference, after successful completion of Phase I, Phase II may be initiated to examine the feasibility of commencing international projects on innovative nuclear energy systems. The paper contains a description of the current and future activities of INPRO and summarizes the outcome of the project.(author)

  12. HVAC system operation manual of IMEF

    International Nuclear Information System (INIS)

    Baek, Sang Yeol; Park, Dae Kyu; Ahn, Sang Bok; Ju, Yong Sun.

    1997-06-01

    This manual is operation procedures of the IMEF(Irradiated Material Examination Facility) HVAC(Heating, Ventilation and Air Conditioning) System. General operation procedures and test method of the IMEF HVAC system are described. The manual is as follows; 1. HVAC system operation manual 2. HVAC system management guide 3. HVAC system maintenance manual 4. HVAC system air velocity and flowrate measurement manual 5. HVAC system HEPA filter leak test manual 6. HVAC system charcoal filter leak test manual 7. HVAC system HEPA and charcoal filter exchange manual. (author). 8 tabs

  13. User requirements and criteria for proliferation resistance in INPRO

    International Nuclear Information System (INIS)

    Choi, K.; Shea, T.E.; Hurt, R.D.; Nishimura, R.

    2004-01-01

    In designing future nuclear energy systems, it is important to consider the potential that such systems could be misused for the purpose of producing nuclear weapons. INPRO set out to provide guidance on incorporating proliferation resistance into innovative nuclear energy systems (INS). Generally two types of proliferation resistance measures are distinguished: intrinsic and extrinsic. Intrinsic features consist of technical design features that reduce the attractiveness of nuclear material for nuclear weapon program, or prevent the diversion of nuclear material or production of undeclared nuclear material for nuclear weapons. Extrinsic measures include commitments, obligations and policies of states such as the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) and IAEA safeguards agreements. INPRO has produced five basic principles and five user requirements for INS. It emphasizes that INS must continue to be an unattractive means to acquire fissile material for a nuclear weapon program. It also addresses as user requirements: 1) a balanced and optimised combination of intrinsic features and extrinsic measures, 2) the development and implementation of intrinsic features, 3) an early consideration of proliferation resistance in the development of INS and 4) the utilization of intrinsic features to increase the efficiency of extrinsic measures. INPRO has also developed criteria, consisting of indicators and acceptance limits, which would be used by a state to assess how an INS satisfies those user requirements. For the first user requirement, the most important but complex one, INPRO provides a 3-layer hierarchy of indicators to assess how unattractive a specific INS would be as part of a nuclear weapon program. Attributes of nuclear material and facilities are used as indicators to assess intrinsic features. Extrinsic measures imposed on the system are also assessed. Indicators to assess defence in depth for proliferation resistance include the number and

  14. A case study for INPRO methodology based on Indian advanced heavy water reactor

    International Nuclear Information System (INIS)

    Anantharaman, K.; Saha, D.; Sinha, R.K.

    2004-01-01

    Under Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a methodology (INPRO methodology) has been developed which can be used to evaluate a given energy system or a component of such a system on a national and/or global basis. The INPRO study can be used for assessing the potential of the innovative reactor in terms of economics, sustainability and environment, safety, waste management, proliferation resistance and cross cutting issues. India, a participant in INPRO program, is engaged in a case study applying INPRO methodology based on Advanced Heavy Water Reactor (AHWR). AHWR is a 300 MWe, boiling light water cooled, heavy water moderated and vertical pressure tube type reactor. Thorium utilization is very essential for Indian nuclear power program considering the indigenous resource availability. The AHWR is designed to produce most of its power from thorium, aided by a small input of plutonium-based fuel. The features of AHWR are described in the paper. The case study covers the fuel cycle, to be followed in the near future, for AHWR. The paper deals with initial observations of the case study with regard to fuel cycle issues. (authors)

  15. Update of the INPRO Collaborative Project, Proliferation Resistance and Safeguard ability Assessment (Prosta) Tools

    Energy Technology Data Exchange (ETDEWEB)

    Chang, H. L.; Kwon, E. H.; Ahn, S. K.; Ko, W. I.; Kim, H. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The objectives of the INPRO Collaborative Project, Proliferation Resistance and Safeguard ability Assessment (PROSA) Tools are to make the INPRO proliferation resistance (PR) assessment methodology simpler and easier to use, to allow for different users and depths of analysis, to demonstrate the value and its usefulness of the refined assessment methodology to potential users, through a test with a reference case, and to provide input to a revision of the INPRO PR assessment manual. A summary of the project is described herein, including the procedure of PR assessment process and a case study using a SFR metal fuel manufacturing facility (SFMF) which is currently in the conceptual design phase at KAERI. The PROSA process with questionnaire approach is simpler and easier to perform that the original INPRO PR methodology with qualitative scale from 'weak' to 'very strong' to be determined by expert judgment. The PROSA process can be applied from the early stage of design showing the relationship of PR assessment to the SBD process.

  16. ISE System Development Methodology Manual

    Energy Technology Data Exchange (ETDEWEB)

    Hayhoe, G.F.

    1992-02-17

    The Information Systems Engineering (ISE) System Development Methodology Manual (SDM) is a framework of life cycle management guidelines that provide ISE personnel with direction, organization, consistency, and improved communication when developing and maintaining systems. These guide-lines were designed to allow ISE to build and deliver Total Quality products, and to meet the goals and requirements of the US Department of Energy (DOE), Westinghouse Savannah River Company, and Westinghouse Electric Corporation.

  17. Progress and status of the international project on innovative nuclear reactors and fuel cycles (INPRO) - 5182

    International Nuclear Information System (INIS)

    Ponomarev, A.; Fesenko, G.; Grigoriev, F.G.; Korinny, A.; Phillips, J.R.; Rho, K.

    2015-01-01

    The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution. INPRO cooperates with Member States to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21. century. INPRO membership has grown to 41 members and 16 observers. The paper presents the current prospectus of the INPRO programme and details the most recent achievements in the following 7 projects: 1) the GAINS project (Global Architecture of Innovative Nuclear Energy Systems with thermal and fast reactors and a closed nuclear fuel cycle); 2) the SYNERGIES project applies and amends the analytical framework developed in GAINS project to examine more specifically the various forms of regional collaboration among nuclear energy suppliers and users; 3) the KIND project (Key Indicators for Innovative Nuclear Energy Systems) has the objective of developing guidance on the evaluation on innovative nuclear technologies; 4) the ROADMAPS project addresses several possible stages toward nuclear energy sustainability; 5) the RISC project aims at demonstrating that the evolution of safety requirements and technical innovations provide continual progress towards the avoidance of evacuation measures outside NPP sites in case of severe accidents; 6) the FANES project has the objective of carrying out feasibility analyses of advanced and innovative fuels for different reactor systems; and 7) the WIRAF project aims at identifying problematic waste from innovative reactor designs and corresponding nuclear fuel cycles

  18. On Brazil's participation in the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO)

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho

    2007-01-01

    In response to a resolution of its 44th General Conference (GC(44)/RES/21) held in September 2000, the International Atomic Energy Agency launched in May 2001 the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO) with the objective of supporting the safe, sustainable, economic and proliferation-resistant use of nuclear technology to meet the global energy needs of the 21st century. Brazil joined the project from its beginnings and in 2005 submitted a proposal for the screening assessment using INPRO methodology of two small-size light-water reactors as potential components of an innovative nuclear reactor system (INS) completed with a conventional open nuclear fuel cycle. The INS reactor components currently being assessed are the International Reactor Innovative and Secure (IRIS) that is being developed by an international consortium made of 21 organizations from 10 countries (Brazil included) led by the Westinghouse Company, and the Fixed Bed Nuclear Reactor (FBNR) that is being developed at the Federal University of Rio Grande do Sul. This paper gives an overview of Brazil's participation in INPRO, highlighting the objective, scope and intermediate results of the assessment study being performed, and the possibilities for participation in one or two collaborative research projects under INPRO Phase 2 Action Plan for 2008-2009. (author)

  19. Economic assessment of the IRIS reactor for deployment in Brazil using INPRO methodology

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho

    2009-01-01

    This paper presents the main results of the evaluation of the economic competitiveness of the International Reactor Innovative and Secure (IRIS) for deployment in Brazil using the assessment methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO was initiated in 2001 and has the main objective of helping to ensure that nuclear energy will be available to contribute in a sustainable manner to the energy needs of the 21st century. Among its missions are the development of a methodology to assess innovative nuclear energy systems (INS) on a global, regional and national basis, and to facilitate the co-operation among IAEA Member States for planning the development and deployment of INS. Brazil joined INPRO since its beginning and in 2005 submitted a proposal for the screening assessment of two small-sized integral-type PWR reactors as alternative components of an INS completed with a conventional open nuclear fuel cycle based on enriched uranium. This paper outlines the rationale and the main results of the economic assessment of the IRIS-based INS completed in August 2008. The study concluded that IRIS reference design satisfies most of INPRO criteria in the area of economics. (author)

  20. Manual control of unstable systems

    Science.gov (United States)

    Allen, R. W.; Hogue, J. R.; Parseghian, Z.

    1986-01-01

    Under certain operational regimes and failure modes, air and ground vehicles can present the human operator with a dynamically unstable or divergent control task. Research conducted over the last two decades has explored the ability of the human operator to control unstable systems under a variety of circumstances. Past research is reviewed and human operator control capabilities are summarized. A current example of automobile directional control under rear brake lockup conditions is also reviewed. A control system model analysis of the driver's steering control task is summarized, based on a generic driver/vehicle model presented at last year's Annual Manual. Results from closed course braking tests are presented that confirm the difficulty the average driver has in controlling the unstable directional dynamics arising from rear wheel lockup.

  1. SNAP operating system reference manual

    International Nuclear Information System (INIS)

    Sabuda, J.D.; Polito, J.; Walker, J.L.; Grant, F.H. III.

    1982-03-01

    The SNAP Operating System (SOS) is a FORTRAN 77 program which provides assistance to the safeguards analyst who uses the Safeguards Automated Facility Evaluation (SAFE) and the Safeguards Network Analysis Procedure (SNAP) techniques. Features offered by SOS are a data base system for storing a library of SNAP applications, computer graphics representation of SNAP models, a computer graphics editor to develop and modify SNAP models, a SAFE-to-SNAP interface, automatic generation of SNAP input data, and a computer graphic post-processor for SNAP. The SOS Reference Manual provides detailed application information concerning SOS as well as a detailed discussion of all SOS components and their associated command input formats. SOS was developed for the US Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the US Naval Surface Weapons Center by Pritsker and Associates, Inc., under contract to Sandia National Laboratories

  2. Proliferation Resistance and Safeguardability Assessment of a SFR Metal Fuel Manufacturing Facility (SFMF) using the INPRO Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Chang, H. L.; Ko, W. I.; Park, S. H.; Kim, H. D.; Park, G. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    To illustrate the proposed Prosta process, to demonstrate its usefulness, and to provide input to a revision of the INPRO manual in the area of proliferation resistance, a case study has been carried out with a conceptually designed sodium cooled fast reactor (SFR) metal fuel manufacturing facility (SFMF), representing novel technology still in the conceptual design phase. A coarse acquisition path analysis has been carried out of the SFMF to demonstrate the assessment process with identified different target materials. The case study demonstrates the usefulness of the proposed PROSA PR assessment process and the interrelationship of the PR assessment with the safeguards-by-design process, identifying potential R and D needs. The PROSA process has been applied to a conceptually designed SFMF, representing novel technology that is still in the conceptual design phase at KAERI. The case study demonstrated that the proposed PROSA process is simpler and easier to perform than the original INPRO methodology and can be applied from the early stage of design showing the relationship of PR assessment to the safeguard-by-design process. New evaluation questionnaire for UR1 is more logical and comprehensive, and provides the legal basis enabling the IAEA to achieve its safeguards objectives including the detection of undeclared nuclear materials and activities. NES information catalogue replacing UR2 was a useful modification and supports safeguardability assessment at the NES and facility level. The proposed PROSA process is also capable to identify strengths and weaknesses of a system in the area of proliferation resistance in a generally understandable form, including R and D gaps that need to be filled in order to meet the criteria for proliferation resistance of a nuclear energy system.

  3. A Study on the Improvement of the INPRO Proliferation Resistance Assessment Methodology

    International Nuclear Information System (INIS)

    Ko, Won Il; Chang, Hong Lae

    2010-07-01

    Within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), a methodology for evaluating proliferation resistance (INPRO PR methodology) has been developed. However, User Requirement (UR) 4 regarding multiplicity and robustness of barriers against proliferation ('innovative nuclear energy systems should incorporate multiple proliferation resistance features and measures') remains to be developed. Because the development of a methodology for evaluating User Requirement 4 requires an acquisition/diversion pathway analysis, a systematic approach was developed for the identification and analysis of pathways for the acquisition of weapons-useable nuclear material. This approach was applied to the DUPIC fuel cycle which identified several proliferation target materials and plausible acquisition/diversion pathways. Based on these results, proliferation strategies that a proliferant State could adopt for undeclared removal of nuclear material from the DUPIC fuel cycle have been developed based on the objectives of the proliferation of the State, the quality and quantity of the target material, the time required to acquire the material for the proliferation, and the technical and financial capabilities of the potential proliferant State. The diversion pathway for fresh DUPIC fuel was analyzed using the INPRO User Requirements 1, 2 and 3, and based on these results an assessment procedure and metrics for evaluating the multiplicity and robustness of proliferation barriers has been developed. In conclusion, the multiplicity and robustness of proliferation barriers is not a function of the number of barriers, or of their individual characteristics but is an integrated function of the whole. The robustness of proliferation barriers is measured by determining whether the safeguards goals can be met. The harmonization of INPRO PR methodology with the GIF PR and PP methodology was also considered. It was suggested that, as also confirmed by IAEA

  4. Manual for a Volunteer Services System.

    Science.gov (United States)

    Helgerson, Linda; And Others

    This manual presents guidelines for planning, monitoring, and controlling the development and operation of volunteer assistance programs. The materials included address questions related to both the process of establishing a volunteer program and the administration of a volunteer management system. The manual is not intended to provide a blueprint…

  5. Manually controlled neutron-activation system

    International Nuclear Information System (INIS)

    Johns, R.A.; Carothers, G.A.

    1982-01-01

    A manually controlled neutron activation system, the Manual Reactor Activation System, was designed and built and has been operating at one of the Savannah River Plant's production reactors. With this system, samples can be irradiated for up to 24 hours and pneumatically transferred to a shielded repository for decay until their activity is low enough for them to be handled at a radiobench. The Manual Reactor Activation System was built to provide neutron activation of solid waste forms for the Alternative Waste Forms Leach Testing Program. Neutron activation of the bulk sample prior to leaching permits sensitive multielement radiometric analyses of the leachates

  6. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). 2011 Progress Report. Enhancing Global Nuclear Energy Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-05-15

    When INPRO was established in 2000, some key characteristics and main objectives for the project were determined and remain basically unchanged to this day: to help ensure that nuclear energy is available to contribute to satisfying energy needs in the 21st century in a sustainable manner and to bring together technology holders, technology users and other stakeholders to consider jointly the national and international actions required to achieve desired innovations in nuclear reactors and fuel cycles. I wish to use the occasion of this INPRO Progress Report to review some of the key highlights of the past year and share with you my views and vision of INPRO's future. The ''Great East Japan Earthquake and Tsunami'' and the resulting accident at TEPCO's Fukushima Daiichi nuclear power plant occurred on 11 March 2011. In response to this accident and at the request of its Member States, the IAEA drafted an Action Plan which defines a programme of work o strengthen the global nuclear safety framework. The activities proposed in the Action Plan are meant to be implemented in the near term, to assess the safety of operating nuclear power plants n the light of lessons learned from the Fukushima Daiichi accident. The assessment covers both technical elements, specifically the design of nuclear power plants with regard to site specific extreme natural hazards, and institutional elements, such as the effectiveness of regulatory bodies, operating organizations and the international legal framework in regard to the implementation of IAEA Safety tandards and Conventions. The lessons learned in the medium and long terms will also be reflected n a periodic update of the design requirements for nuclear power plants, international safety tandards, regulations issued by national supervisory authorities, operational procedures, emergency planning and safety assessment methodologies. INPRO has a long term perspective and provides an assessment of the whole nuclear system. Ensuring

  7. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). 2011 Progress Report. Enhancing Global Nuclear Energy Sustainability

    International Nuclear Information System (INIS)

    2012-05-01

    When INPRO was established in 2000, some key characteristics and main objectives for the project were determined and remain basically unchanged to this day: to help ensure that nuclear energy is available to contribute to satisfying energy needs in the 21st century in a sustainable manner and to bring together technology holders, technology users and other stakeholders to consider jointly the national and international actions required to achieve desired innovations in nuclear reactors and fuel cycles. I wish to use the occasion of this INPRO Progress Report to review some of the key highlights of the past year and share with you my views and vision of INPRO's future. The ''Great East Japan Earthquake and Tsunami'' and the resulting accident at TEPCO's Fukushima Daiichi nuclear power plant occurred on 11 March 2011. In response to this accident and at the request of its Member States, the IAEA drafted an Action Plan which defines a programme of work o strengthen the global nuclear safety framework. The activities proposed in the Action Plan are meant to be implemented in the near term, to assess the safety of operating nuclear power plants n the light of lessons learned from the Fukushima Daiichi accident. The assessment covers both technical elements, specifically the design of nuclear power plants with regard to site specific extreme natural hazards, and institutional elements, such as the effectiveness of regulatory bodies, operating organizations and the international legal framework in regard to the implementation of IAEA Safety tandards and Conventions. The lessons learned in the medium and long terms will also be reflected n a periodic update of the design requirements for nuclear power plants, international safety tandards, regulations issued by national supervisory authorities, operational procedures, emergency planning and safety assessment methodologies. INPRO has a long term perspective and provides an assessment of the whole nuclear system. Ensuring

  8. The international project on innovative nuclear reactors and fuel cycles (INPRO): status and outlook

    International Nuclear Information System (INIS)

    Steur, R.; Kupitz, J.; Depisch, F.

    2004-01-01

    Full text: During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also new requirements for the way the energy will be supplied have to be fulfilled. Following a resolution of the General Conference of the IAEA in the year 2000 an International Project on Innovative Nuclear Reactors and Fuel Cycles, referred to as INPRO, was initiated. The main objectives of INPRO are to: Help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner; and Bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles. Within INPRO the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, requirements for the different aspects of the future of nuclear energy systems, such as economics, sustain ability and environment, safety, waste and proliferation resistance have been identified as well a methodology developed. to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also different aspects of the infrastructure, technical as well institutional have been reviewed and recommendations for changes are made to anticipate main developments in the world such as the ongoing globalisation. As a contribution to the conference

  9. Current status and future direction of INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles)

    International Nuclear Information System (INIS)

    Omoto, Akira; Moriwaki, Masanao; Sugimoto, Jun; Nakai, Ryodai

    2007-01-01

    INPRO is an international forum to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles so as to ensure that nuclear energy is available to contribute to a sustainable development of the human, and IAEA becomes the secretariat for INPRO. The number of the members counts 28 by recent participation of Japan and U.S.A. now, and it is a unique forum to bring together both technology users and technology holders, that includes 5 countries which do not still have nuclear power generation. Until now it was phase I, and focused its activities to make clear the desired characteristics of nuclear energy system toward the future, and to develop methodology to evaluate various nuclear energy systems, but it shifted to phase II from July, 2006, and it planned three areas of activities such as improvement of evaluation methodology, institutional/infrastructure oriented activities and a collaborative project of technology development. Current status and future direction of INPRO was presented to encourage Japan in significant contributions of these three areas. (T. Tanaka)

  10. INPRO economic assessment of the IRIS nuclear reactor for deployment in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves Filho, Orlando Joao Agostinho, E-mail: orlando@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN - RJ), Rua Helio de Almeida, 75, Cidade Universitaria, Ilha do Fundao, 21941-906 Rio de Janeiro, RJ (Brazil)

    2011-06-15

    Highlights: > First INPRO evaluation of IRIS economic competitiveness for deployment in Brazil. > Plant arrangement of three independent IRIS single units constructed in series. > Angra 3 reactor used as reference design for judgment of IRIS economic potential. > IRIS economically competes with 2nd generation nuclear power plants in Brazil - Abstract: This paper presents the results of the economic assessment of the International Reactor Innovative and Secure (IRIS) for deployment in Brazil using the assessment methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO initiated in 2001 and has the main objective of helping to ensure that nuclear energy will be available to contribute in a sustainable manner to the energy needs of the 21st century. Among its missions is the development of a methodology to assess innovative nuclear energy systems (INSs) on a global, regional and national basis. In 2005, Brazil submitted a proposal for the assessment of two small-size reactors as components of an INS, completed with a conventional open nuclear fuel cycle based on enriched uranium. One of the reactors assessed was IRIS, a small-size, modular, integral-type PWR reactor. IRIS was evaluated with regard to the areas of reactor safety and economics only. This paper outlines the rationale for the study and summarizes the results of the economic assessment. The study concluded that the reference design of IRIS complies with most of INPRO economics criteria and has potential to comply with the remaining ones.

  11. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). 2008 progress report

    International Nuclear Information System (INIS)

    2009-02-01

    The purpose of the work is to review the progress of the IAEA international project for innovative reactors and fuel cycle technologies (INPRO). The publication reports about the recognition of INPRO and on general Information on INPRO, its strengths, memberships, collaboration with other international initiatives, the INPRO organization and management and the history of INPRO. The section on the progress of INPRO in 2008 contains task 1: INPRO Methodology, task 2: Assessment Studies, task 3: Nuclear Energy Visions for the 21st Century, task 4: Infrastructure and Institutional Innovation, task 5: Common User Considerations and task 6: Collaborative Projects. Conclusions and New Trends are followed by a bibliography. Annex I deals with the INPRO project management in 2008 and Annex II provides a selection of photographs from 2008. Finally a list of acronyms is provided

  12. Assessment of two small-sized innovative nuclear reactors for electricity generation in Brazil using INPRO methodology

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho; Sefidvash, Farhang

    2009-01-01

    This paper presents the main results of the assessment study of two small-sized innovative reactors for electricity generation in Brazil using the methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO was initiated in 2001 and has the main objective of helping to ensure that nuclear energy is available to contribute in a sustainable manner to the energy needs of the 21st century. Brazil joined the INPRO project since its beginning and in 2005 submitted a proposal for the assessment using INPRO methodology of two small-sized reactors (IRIS - International Reactor Innovative and Secure, and FBNR - Fixed Bed Nuclear Reactor) as potential components of an innovative nuclear energy system (INS) completed by a conventional open nuclear fuel cycle based on enriched uranium. The scope of this assessment study was restricted to the reactor component of the INS and to the methodology areas of economics and safety for IRIS, and proliferation resistance and safety for FBNR. The results indicate that both IRIS and FBNR innovative designs comply mostly with the basic principles of the areas assessed and have potential to comply with the remaining ones. (author)

  13. Technical progress in INPRO activities on modelling and innovation

    International Nuclear Information System (INIS)

    Villalibre, P.; Haas, E.; Khartabil, H.; Kim, S.; Korinny, A.; Usanov, V. and others

    2010-01-01

    Among the 31 Members of the 'International Project on Innovative Nuclear Reactors and Fuel Cycles' (INPRO) in April 2010, more than 20 are cooperating in the implementation of Collaborative Projects (CPs) related to the four substantive Programme Areas of the INPRO Action Plan. The purpose of the CPs is to contribute to the achievement of goals established in the programmatic areas. This paper presents progress status of several CPs dealing with Modelling and Innovation: - CP on Environmental Impact Benchmarking applicable to Nuclear Energy Systems under Normal Operation (ENV): A benchmark of codes and methods for determining radiation released during normal operation of nuclear facilities is performed by using established source term, release scenario, and target group (humans). - CP on Proliferation Resistance: Acquisition/Diversion Pathway Analysis (PRADA): 'PRADA' addresses the identification and analyses of high level pathways for the acquisition of weapons usable material, and makes recommendations for evaluating the multiplicity and robustness of barriers against proliferation. PRADA develops a case study based on DUPIC fuel cycle. The outcome from the project will support the assessment methodologies developed at GIF and INPRO. - CP on Global Architecture of Nuclear Energy Systems based on Thermal and Fast Reactors including Closed Fuel Cycle (GAINS): GAINS objective is to develop a methodological platform for assessing future nuclear energy systems taking into account the sustainable development, and to validate the results through sample analyses. High and moderate scenarios of nuclear energy demand and supply during the Century (5000 and 2500 GWe respectively in the year 2100) are being analysed using homogeneous and heterogeneous considerations. A non-geographic approach grouping the countries according to their planned use of nuclear energy has being established. - CP on Investigations of the 233 U/Th Fuel Cycle (ThFC): ThFC objective is to explore FC

  14. Methodology for the assessment of innovative nuclear reactors and fuel cycles. Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2004-12-01

    an innovative nuclear energy system (INS) to meet the overall target of sustainable energy supply. As well, the initial development of the INPRO method for the assessment of nuclear energy systems was carried out. The Basic Principles, User Requirements, and Criteria and the INPRO method of assessment, taken together, comprise the INPRO methodology. The INPRO methodology provides the possibility to take into account local, regional and global boundary conditions of IAEA Member States, including those of both developing and developed countries. Phase 1A was completed in June of 2003 with the publication of IAEA-TECDOC-1362, Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles, which documented the results of the Phase 1A work. The next step of INPRO was immediately launched. In this step, referred to as Phase 1B (first part), INPRO arranged for some 14 case studies to be performed, by national teams or by individual experts from seven countries, to test and provide feedback on the applicability, consistency and completeness of the INPRO methodology. This report documents changes to the basic principles, user requirements, criteria and the method of assessment that resulted from the second step of INPRO (referred to as Phase 1B (first part)), which started in June 2003 and ended in December 2004. During this step, Member States and individual experts performed 14 case studies with the objective of testing and validating the INPRO methodology. Based on the feedback from these case studies and numerous consultancies mostly held at the IAEA, the INPRO methodology has been significantly updated and revised, as documented in this report. The ongoing and future activities of INPRO will lead to further modifications to the INPRO methodology, based on the feedback received from Member States in light of their experience in applying the methodology. Thus, additional reports will be issued, as appropriate, to update the INPRO methodology

  15. The IAEA international project on innovative nuclear reactors and fuel cycles (INPRO): Status, ongoing activities and outlook

    International Nuclear Information System (INIS)

    Kupitz, J.; Depisch, F.; Khorochev, M.

    2004-01-01

    The IAEA General Conference (2000) invited 'all interested Member States to combine their efforts under the aegis of the IAEA in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology'. In response to this invitation, the IAEA initiated the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). The overall objectives of INPRO are to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21 st century in a sustainable manner; and to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles. INPRO is addressing the identification of full spectrum of user requirements for innovative technologies as well as the development of methodologies and guidelines for the comparison of different innovative approaches taking into account variations in potential demands across countries. INPRO can make major contributions by focusing on economic aspects, and societal acceptability issues and those areas where IAEA can make unique contributions such as proliferation resistance, nuclear safety, waste management and sustainability issues and providing assistance to the user community. To enhance the potential for the deployment of innovative technologies, some changes in the infrastructure under which nuclear energy is developed and used; should be envisaged. In order to fulfil these objectives, the first phase of INPRO dealt with the development of a methodology to assess and compare the performance of innovative nuclear energy systems (INS). This methodology includes the definition of a set of Basic principles, User requirements and Criteria to be met in different areas (Economics, Sustainability and environment, Safety of nuclear installations, Waste management and Proliferation resistance). The result of

  16. NJOY nuclear data processing system: user's manual

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Barrett, R.J.; Muir, D.W.; Boicourt, R.M.

    1978-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. This user's manual provides a concise description of the code, input instructions, sample problems, and installation instructions. 1 figure, 3 tables

  17. RHCV Telescope System Operations Manual

    Science.gov (United States)

    2018-01-05

    KRISTOFFER A. SMITH-RODRIGUEZ, LTCOL, USAF Chief, Warfighter Interface Division Airman Systems Directorate This report is published in the...other system components via ASCOM protocols. 1. Start the MaxImDL application using the desktop shortcut (a) Start Observatory dialog, (b...the desktop shortcut (a) Select “Connect Telescope” from Startup menu in Telescope tab (b) Select “Look Up” icon on ribbon menu at the top right of

  18. Airport Information Retrieval System (AIRS) System Support Manual

    Science.gov (United States)

    1973-01-01

    This handbook is a support manual for prototype air traffic flow control automation system developed for the FAA's Systems Command Center. The system is implemented on a time-sharing computer and is designed to provide airport traffic load prediction...

  19. Hanford Environmental Information System (HEIS) user's manual

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. Data stored in the HEIS are collected under several regulatory programs. Currently these include the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and the Ground-Water Environmental Surveillance Project, managed by the Pacific Northwest Laboratory. The HEIS is an information system with an inclusive database. The manual, the HEIS User's Manual, describes the facilities available to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines

  20. INPRO Collaborative Project: Proliferation Resistance: Acquisition/Diversion Pathway Analysis (PRADA)

    International Nuclear Information System (INIS)

    2012-05-01

    This publication contributes to strengthening the assessment area of proliferation resistance of the INPRO methodology. The basic principle for this area requires that multiple intrinsic features and extrinsic measures of proliferation resistance be implemented throughout the full life cycle of an innovative nuclear energy system to help ensure that the system will continue to be an unattractive means of acquiring fissile material for a nuclear weapons programme. A typical intrinsic feature is the dilution of plutonium with fission products as found in irradiated material, and a typical extrinsic measure is the placing of nuclear material under international safeguards.

  1. Major Findings of the IAEA/INPRO Collaborative Project on Global Architectures of Innovative Nuclear Energy Systems with Thermal and Fast Reactors and a Closed Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Kuznetsov, V.; Fesenko, G.; Kriachko, M.; Dixon, B.; Hayashi, H.; Usanov, V.

    2013-01-01

    GAINS objectives: Rationale: • Increasing interest in MSs in joint modelling of global and regional trends in nuclear power taking into account technical innovations and multilateral cooperation; • Modelling of the kind requires agreed methodological platform to analyse transition strategies from the present to future nuclear energy system (NES). Overall objectives: Address technical & institutional issues of developing a global architecture for the sustainable NES in the 21st century: • develop a framework (common methodological platform, databases, assumptions & boundary conditions); • perform sample studies; • indicate potential areas for application of GAINS framework

  2. Performance Assessment of Passive Gaseous Provisions (PGAP). Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-07-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in 2000 on the basis of IAEA General Conference resolution GC(44)/RES/21. INPRO helps to ensure the availability of sustainable nuclear energy in the 21st century and seeks to bring together all interested Member States - both technology holders and technology users - to consider joint actions to achieve desired innovations. To contribute to an international consensus on the definition of the reliability of passive systems that involve natural circulation, and on a methodology to assess this reliability, INPRO initiated a collaborative project on Performance Assessment of Passive Gaseous Provisions (PGAP) in 2007. Advanced nuclear reactor designs incorporate several passive systems in addition to active ones, not only to enhance the operational safety of the reactors but also to mitigate the consequences of a severe accident should one occur. However, the reliability of passive safety systems is crucial and must be assessed before they are used extensively in future nuclear power plants. Several physical parameters affect the performance of a passive safety system, and their values at the time of operation are a priori unknown. The functions of many passive systems are based on thermohydraulic principles, which until recently were considered as not being subject to any kind of failure. Hence, large and consistent efforts are required to quantify the reliability of such systems. Three participants from three INPRO Member States were involved in this collaborative project. Reliability methods for passive systems (RMPS) and assessment of passive system reliability (APSRA) methodologies were used by the participants to assess the performance and reliability of the passive decay heat removal system of the French gas cooled fast reactor design for station blackout and a loss of coolant accident combined with loss of off-site power, respectively. This publication presents the

  3. 21 CFR 892.5650 - Manual radionuclide applicator system.

    Science.gov (United States)

    2010-04-01

    ... system. (a) Identification. A manual radionuclide applicator system is a manually operated device... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Manual radionuclide applicator system. 892.5650.... This generic type of device may include patient and equipment supports, component parts, treatment...

  4. Clean Lead Facility Inventory System user's manual

    International Nuclear Information System (INIS)

    Garcia, J.F.

    1994-12-01

    The purpose of this user's manual is to provide instruction and guidance needed to enter and maintain inventory information for the Clean Lead Facility (CLF), PER-612. Individuals responsible for maintaining and using the system should study and understand the information provided. The user's manual describes how to properly use and maintain the CLF Inventory System. Annual, quarterly, monthly, and current inventory reports may be printed from the Inventory System for reporting purposes. Profile reports of each shipment of lead may also be printed for verification and documentation of lead transactions. The CLF Inventory System was designed on Microsoft Access version 2.0. Similar inventory systems are in use at the Idaho National Engineering Laboratory (INEL) to facilitate site-wide compilations of mixed waste data. The CLF Inventory System was designed for inventorying the clean or non-radioactive contaminated lead stored at the CLF. This data, along with the mixed waste data, will be compiled into the Idaho Mixed Waste Information (IMWI) system for reporting to the Department of Energy Idaho Office, Department of Energy Headquarters, and/or the State of Idaho

  5. International Cooperation for the next 50 years: The International Project on Innovative Reactors and Fuel Cycles (INPRO)

    Energy Technology Data Exchange (ETDEWEB)

    Kupitz, J.; Steur, R.; Depisch, F. [IAEA, Wagramerstrasse 5, PF 100, 1400 Vienna (Austria)]. e-mail: J.Kupitz@iaea.org

    2004-07-01

    During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also the requirements for the way the energy will be supplied. Within INPRO the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, an inventory of requirements for the future of nuclear energy systems has been collected as well a methodology developed by INPRO to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also the infrastructure, technical as well institutional has to be adjusted to the anticipated changes in the world such as the globalization. As a contribution to the conference the main messages of INPRO will be presented. (Author)

  6. International Cooperation for the next 50 years: The International Project on Innovative Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    Kupitz, J.; Steur, R.; Depisch, F.

    2004-01-01

    During the last fifty years remarkable results are achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also the requirements for the way the energy will be supplied. Within INPRO the future of the energy demand and supply was explored and several scenario's identified. A leading requirement for energy supply is coming up and will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is as well an important issue. Based on these scenario's for the next fifty years, an inventory of requirements for the future of nuclear energy systems has been collected as well a methodology developed by INPRO to assess innovative nuclear systems and fuel cycles. On the base of this assessment, the need for innovations and breakthroughs in existing technology can be defined. To facilitate the deployment of innovative nuclear systems also the infrastructure, technical as well institutional has to be adjusted to the anticipated changes in the world such as the globalization. As a contribution to the conference the main messages of INPRO will be presented. (Author)

  7. Hazardous Solvent Substitution Data System reference manual

    International Nuclear Information System (INIS)

    Branham-Haar, K.A.; Twitchell, K.E.

    1993-07-01

    Concern for the environment, in addition to Federal regulation, mandate the replacement of hazardous solvents with safer cleaning agents. Manufacturers are working to produce these replacement solvents. As these products are developed, potential users need to be informed of their availability. To promote the use of these new products instead of traditional solvents, the Idaho National Engineering Laboratory (INEL) has developed the Hazardous Solvent Substitution Data System (HSSDS). The HSSDS provides a comprehensive system of information on alternatives to hazardous solvents and related subjects, and it makes that information available to solvent users, industrial hygienists, and process engineers. The HSSDS uses TOPIC reg-sign, a text retrieval system produced by Verity, Inc., to allow a user to search for information on a particular subject. TOPIC reg-sign produces a listing of the retrieved documents and allows the use to examine the documents individually and to use the information contained in them. This reference manual does not replace the comprehensive TOPIC reg-sign user documentation (available from Verity, Inc.), or the HSSDS Tutorial (available from the INEL). The purpose of this reference manual is to provide enough instruction on TOPIC reg-sign so the user may begin accessing the data contained in the HSSDS

  8. The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO): General description and implications for the research reactor infrastructure needed for R and D

    International Nuclear Information System (INIS)

    Sokolov, Yury A.

    2005-01-01

    The substantial growth in 21st century energy supplies needed to meet sustainable development goals has been emphasized by UNCSD, WSSD, IPCC and others. This will be driven by continuing population growth, economic development and aspiration to provide access to modern energy systems to the 1,6 billion people now without such access, the growth demand on limiting greenhouse gas emissions, and reducing the risk of climate change. A key factor to the future of nuclear power is the degree to which innovative nuclear technologies can be developed to meet challenges of economic competitiveness, safety, waste and proliferation concerns. There are two major international initiatives in the area of innovative nuclear technology: the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycle (INPRO) and the Generation IV International Forum. With INPRO some scenarios of future energy needs were identified and the methodology for holistic assessment of the innovative nuclear energy systems (INS), which can be developed to meet these scenarios, was developed.. The current status of the INPRO project and details of the INPRO methodology will be reported. The research needs identified due to Agency's activities on innovative nuclear system development assume the use of research reactors. The areas crucial for the development of INS which critically dependent of the RR experiments and following requirements addressed to the RR will be discussed. These areas include the development of advanced fuel and core materials for proposed innovative power reactor concepts. (author)

  9. The IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO): Status, Ongoing Activities and Outlook

    International Nuclear Information System (INIS)

    Kupitz, Juergen; Depisch, Frank; Azpitarte, Osvaldo

    2004-01-01

    The IAEA General Conference (2000) invited 'all interested Member States to combine their efforts under the aegis of the IAEA in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology'. In response to this invitation, the IAEA initiated the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). The overall objectives of INPRO are to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21. century in a sustainable manner, and to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles. In order to fulfil these objectives, the first phase of INPRO dealt with the development of a methodology to assess and compare the performance of innovative nuclear energy systems. This methodology includes the definition of a set of Basic principles, User requirements and Criteria to be met in different areas (Economics, Sustainability and environment, Safety of nuclear installations, Waste management and Proliferation resistance). The result of this phase was presented in a IAEA document (IAEA-TECDOC-1362, Guidance for the evaluation of innovative nuclear reactors and fuel cycles) issued in June 2003. In the present phase of the project, case studies are being carried out in order to validate and improve the developed methodology and the defined set of Basic principles, User requirements and Criteria. This paper shortly summarizes the results published in IAEA-TECDOC-1362 and the ongoing actions related to case studies. Finally, an outlook of INPRO activities is presented. (authors)

  10. Uranium concentration monitor manual: 2300 system

    International Nuclear Information System (INIS)

    Russo, P.A.; Sprinkle, J.K. Jr.; Stephens, M.M.

    1985-04-01

    This manual describes the design, operation, and procedures for measurement control for the automated uranium concentration monitor on the 2300 solvent extraction system at the Oak Ridge Y-12 Plant. The nonintrusive monitor provides a near-real time readout of uranium concentration at two locations simultaneously in the solvent extraction system for process monitoring and control. Detectors installed at the top of the extraction column and at the bottom of the backwash column acquire spectra of gamma rays from the solvent extraction solutions in the columns. Pulse-height analysis of these spectra gives the concentration of uranium in the organic product of the extraction column and in the aqueous product of the solvent extraction system. The visual readouts of concentrations for process monitoring are updated every 2 min for both detection systems. Simultaneously, the concentration results are shipped to a remote computer that has been installed by Y-12 to demonstrate automatic control of the solvent extraction system based on input of near-real time process operation information. 8 refs., 13 figs., 4 tabs

  11. Explosives Classifications Tracking System User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Genoni, R.P.

    1993-10-01

    The Explosives Classification Tracking System (ECTS) presents information and data for U.S. Department of Energy (DOE) explosives classifications of interest to EM-561, Transportation Management Division, other DOE facilities, and contractors. It is intended to be useful to the scientist, engineer, and transportation professional, who needs to classify or transport explosives. This release of the ECTS reflects upgrading of the software which provides the user with an environment that makes comprehensive retrieval of explosives related information quick and easy. Quarterly updates will be provided to the ECTS throughout its development in FY 1993 and thereafter. The ECTS is a stand alone, single user system that contains unclassified, publicly available information, and administrative information (contractor names, product descriptions, transmittal dates, EX-Numbers, etc.) information from many sources for non-decisional engineering and shipping activities. The data is the most up-to-date and accurate available to the knowledge of the system developer. The system is designed to permit easy revision and updating as new information and data become available. These, additions and corrections are welcomed by the developer. This user manual is intended to help the user install, understand, and operate the system so that the desired information may be readily obtained, reviewed, and reported.

  12. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Introduction and status

    International Nuclear Information System (INIS)

    2002-01-01

    INPRO is a response to the invitation of the IAEA General Conference to combine efforts in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation resistant nuclear technology. The objective if INPRO is to support the safe, sustainable, economic and proliferation-resistant use of nuclear technology to meet the global energy needs of the 21st century

  13. On Brazil participation in the first ten years of the INPRO Project and perceptivities ahead

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho

    2011-01-01

    In September 2001, the International Atomic Energy Agency (IAEA) launched the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) to help ensure that nuclear energy is available to contribute to meeting the world energy needs of the 21st century in a sustainable manner. To achieve its objective INPRO brings together technology holders and technology users to consider jointly the international and the national actions to achieve the desired innovations in nuclear reactors, fuel cycles and institutional approaches. This paper reviews INPRO's main achievements in its first ten years of existence and highlights Brazil's contributions to the project and the benefits gained from its membership. Among INPRO's main achievements are the development of the INPRO assessment methodology, key studies and collaborative project results, and the establishment of the Dialogue Forum between technology holders and technology users. Brazil contributed to the project by providing a cost-free expert to the INPRO Coordination Group in 2002, by performing an assessment of two small sized reactors for deployment in the country using INPRO methodology published in 2009, and by participating in two collaborative projects related to technology innovations, which shall be completed by the end of this year. The paper concludes with a short presentation of the opportunities for the country's participation in the activities of the INPRO Action Plan for the biennium 2012-2013, currently under preparation. (author)

  14. Next Generation Nuclear Plant System Requirements Manual

    International Nuclear Information System (INIS)

    Not Listed

    2008-01-01

    System Requirements Manual for the NGNP Project. The Energy Policy Act of 2005 (H.R. 6; EPAct), which was signed into law by President George W. Bush in August 2005, required the Secretary of the U.S. Department of Energy (DOE) to establish a project to be known as the Next Generation Nuclear Plant (NGNP) Project. According to the EPAct, the NGNP Project shall consist of the research, development, design, construction, and operation of a prototype plant (to be referred to herein as the NGNP) that (1) includes a nuclear reactor based on the research and development (R and D) activities supported by the Generation IV Nuclear Energy Systems initiative, and (2) shall be used to generate electricity, to produce hydrogen, or to both generate electricity and produce hydrogen. The NGNP Project supports both the national need to develop safe, clean, economical nuclear energy and the Nuclear Hydrogen Initiative (NHI), which has the goal of establishing greenhouse-gas-free technologies for the production of hydrogen. The DOE has selected the helium-cooled High Temperature Gas-Cooled Reactor (HTGR) as the reactor concept to be used for the NGNP because it is the only near-term Generation IV concept that has the capability to provide process heat at high-enough temperatures for highly efficient production of hydrogen. The EPAct also names the Idaho National Laboratory (INL), the DOE's lead national laboratory for nuclear energy research, as the site for the prototype NGNP

  15. Assessment of Deafblind Access to Manual Language Systems (ADAMLS)

    Science.gov (United States)

    Blaha, Robbie; Carlson, Brad

    2007-01-01

    This document presents the Assessment of Deafblind Access to Manual Language Systems (ADAMLS), a resource for educational teams who are responsible for developing appropriate adaptations and strategies for children who are deafblind who are candidates for learning manual language systems. The assessment tool should be used for all children with a…

  16. Preliminary Study Intended for the Application of the INPRO Methodology in the area of Infrastructure (Public Acceptance) for the Case of Mexico

    International Nuclear Information System (INIS)

    Heredia, R.; Puente Espel, F.

    2016-01-01

    The pronounced concern about climate change as seen in the past COP21 Conference, the increasing energy demand worldwide, and the importance of energy security are among the main issues within the pursuit of a sustainable development. In a sustainable and diverse energy portfolio, the goals focus on providing clean, carbon free, reliable and affordable electricity. Nuclear energy is one of the most efficient energy sources; considering the energy produced per amount of fuel, one of the least climate dependent sources and a clean energy source. Nuclear energy is a sustainable energy source. But the sustainability of nuclear energy systems is questioned by the public, as well as by some decision makers, mainly due to concerns related to safety, nuclear waste disposal, and the proliferation of nuclear weapons. The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), from the International Atomic Energy Agency (IAEA), was established to assist and guarantee that in order to meet the energy needs of the 21st century through a sustainable approach, nuclear energy is available. In this line, INPRO in close cooperation with Member States work to understand the future development of nuclear energy systems from a national, regional and global perspective, as well as to comprehend the role of innovation in technologies and institutional arrangements in support of this development. Through one of INPRO's main areas, Sustainability Assessment and Strategies, INPRO supports Member States in developing national long-range sustainable nuclear energy strategies and related deployment decision-making throughout the application of the INPRO Methodology. This paper presents a preliminary study intended for the application of the INPRO Methodology in the area of Infrastructure, Public Acceptance, for the case of Mexico. Mexico's current nuclear power programme is small; integrated by a nuclear power plant (NPP) with two reactors. In the scenario of a

  17. The IAEA international project on innovative nuclear reactors and fuel cycles (INPRO): study on opportunities and challenges of large-scale nuclear energy development

    International Nuclear Information System (INIS)

    Khoroshev, M.; Subbotin, S.

    2006-01-01

    Existing scenarios for global energy use project that demand will at least double over the next 50 years. Electricity demand is projected to grow even faster. These scenarios suggest that the use of all available generating options, including nuclear energy, will inevitably be required to meet those demands. If nuclear energy is to play a meaningful role in the global energy supply in the foreseeable future, innovative approaches will be required to address concerns about economic competitiveness, environment, safety, waste management, potential proliferation risks and necessary infrastructure. In the event of a renaissance of nuclear energy, adequate infrastructure development will become crucial for Member States considering the future use of nuclear power. The IAEA should be ready to provide assistance in this area. A special resolution was adopted by the General Conference in September 2005 on 'Strengthening the Agency's Activities Related to Nuclear Science, Technology and Applications: Approaches to Supporting Nuclear Power Infrastructure Development'. Previously, in 2000, taking into account future energy scenarios and the needs of Member States, the IAEA General Conference had adopted a resolution initiating the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Based on scenarios for the next fifty years, INPRO identified requirements for different aspects of future nuclear energy systems, such as economics, environment, safety, waste management, proliferation resistance and infrastructure and developed a methodology to assess innovative nuclear systems and fuel cycles. Using this assessment tool, the need for innovations in nuclear technology can be defined, which can be achieved through research, development and demonstration (RD and D). INPRO developed these requirements during its first stage, Phase 1A, which lasted from 2001 to mid-2003. In the second stage, Phase 1B (first part), INPRO organized 14 case studies (8 by

  18. Manual on maintenance of systems and components important to safety

    International Nuclear Information System (INIS)

    1986-01-01

    The Manual should serve as guidance at the plant management level for the maintenance of systems and components important to safety. It includes a detailed description of management systems, administrative controls and procedures. The Annexes contain examples of documents and practices adopted by Operating Organizations of some Member States. It is not the intention of this Manual to address the technical problem of how to maintain a particular component but rather to cover the programmatic aspects of maintenance. It also contains some aspects of surveillance and verification activities. The Manual makes only general statements about radiation protection provisions in connection with maintenance; detailed guidance can be found in other IAEA documents

  19. Tank waste remediation system process engineering instruction manual

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    1998-01-01

    The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees

  20. Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors. Report of the collaborative project COOL of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-05-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO aims at helping to ensure that nuclear energy is available in the twenty-first century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to jointly consider actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. One of the aims of INPRO is to develop options for enhanced sustainability through promotion of technical and institutional innovations in nuclear energy technology through collaborative projects among IAEA Member States. Collaboration among INPRO members is fostered on selected innovative nuclear technologies to bridge technology gaps. Collaborative projects have been selected so that they complement other national and international R and D activities. The INPRO Collaborative Project COOL on Investigation of Technological Challenges Related to the Removal of Heat by Liquid Metal and Molten Salt Coolants from Reactor Cores Operating at High Temperatures investigated the technological challenges of cooling reactor cores that operate at high temperatures in advanced fast reactors, high temperature reactors and accelerator driven systems by using liquid metals and molten salts as coolants. The project was initiated in 2008 and was led by India; experts from Brazil, China, Germany, India, Italy and the Republic of Korea participated and provided chapters of this report. The INPRO Collaborative Project COOL addressed the following fields of research regarding liquid metal and molten salt coolants: (i) survey of thermophysical properties; (ii) experimental investigations and computational fluid dynamics studies on thermohydraulics, specifically pressure drop and heat transfer under different operating conditions; (iii) monitoring and control of coolant

  1. Manual for THOR-AirPAS - air pollution assessment system

    DEFF Research Database (Denmark)

    Jensen, Steen Solvang; Ketzel, Matthias; Brandt, Jørgen

    The report provides an outline of the THOR-AirPAS - air pollution assessment system and a brief manual for getting started with the air quality models and input data included in THOR-AirPAS.......The report provides an outline of the THOR-AirPAS - air pollution assessment system and a brief manual for getting started with the air quality models and input data included in THOR-AirPAS....

  2. Proliferation Resistance and Safeguards by Design: The Safeguardability Assessment Tool Provided by the INPRO Collaborative Project ''INPRO'' (Proliferation Resistance and Safeguardability Assessment)

    International Nuclear Information System (INIS)

    Haas, E.; Chang, H.-L.; Phillips, J.R.; Listner, C.

    2015-01-01

    Since the INPRO Collaborative Project on Proliferation Resistance and Safeguardability Assessment Tools (PROSA) was launched in 2011, Member State experts have worked with the INPRO Section and the IAEA Department of Safeguards to develop a revised methodology for self-assessment of sustainability in the area of proliferation resistance of a nuclear energy system (NES). With the common understanding that there is ''no proliferation resistance without safeguards'' the revised approach emphasizes the evaluation of a new 'User Requirement' for ''safeguardability'', that combines metrics of effective and efficient implementation of IAEA Safeguards including ''Safeguards-by-Design'' principles. The assessment with safeguardability as the key issue has been devised as a linear process evaluating the NES against a ''Basic Principle'' in the area of proliferation resistance, answering fundamental questions related to safeguards: 1) Do a State's legal commitments, policies and practices provide credible assurance of the exclusively peaceful use of the NES, including a legal basis for verification activities by the IAEA? 2) Does design and operation of the NES facilitate the effective and efficient implementation of IAEA safeguards? To answer those questions, a questionnaire approach has been developed that clearly identifies gaps and weaknesses. Gaps include prospects for improvements and needs for research and development. In this context, the PROSA approach assesses the safeguardability of a NES using a layered ''Evaluation Questionnaire'' that defines Evaluation Parameters (EP), EP-related questions, Illustrative Tests and Screening Questions to present and structure the evidence of findings. An integral part of the assessment process is Safeguards-by-Design, the identification of potential diversion, misuse and concealment strategies (coarse diversion path

  3. Status of INPRO collaborative project PGAP

    International Nuclear Information System (INIS)

    Khartabil, Hussam

    2011-01-01

    Performance Assessment of Passive Gaseous Provision – PGAP: • Objectives: • Contribute to an international consensus on the definition of the reliability of a Category B passive system; • Contribute to a methodology to assess this reliability; • Scope: • Benchmark studies; • Discussion and comparison of methodologies; • Proposal for a common definition for the reliability of a passive system and a common methodology to assess it

  4. The IAEA international project on innovative nuclear reactors and fuel cycles (INPRO):status, development of approaches and outlook

    International Nuclear Information System (INIS)

    Khoroshev, M.; Sokolov, Y.; Facer, I.

    2005-01-01

    During the last fifty years remarkable results have been achieved in the application of nuclear technology for the production of electricity. Looking ahead to the next fifty years it is clear that the demand for energy will grow considerably and also new requirements have to be fulfilled for the way nuclear energy will be supplied, UNCSD, WSSD, IPCC and others have emphasized the substantial growth in 21st century energy supplies needed to meet sustainable development (SD) goals. This will be driven by continuing population growth, economic development and aspiration to provide access to modern energy systems to be 1,6 billion people now without such access, the growth demand on limiting greenhouse gas emissions, and reducing the risk oaf climate change. A key factor to the future of nuclear power is the degree to which innovative nuclear technologies can be developed to meet challenges of economic competitiveness, safety,waste and proliferation concerns. There are two major international initiatives in the area of innovative nuclear technology: the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycle (INPRO) and the Generation IV International Forum. Following a resolution of the General Conference of the IAEA in the year 2000 an International Project on Innovative Nuclear Reactors and Fuel Cycles, referred to as INPRO, was initiated (Authors)

  5. The users manual and concepts of nuclear materials accounting system

    International Nuclear Information System (INIS)

    Lee, Byung Du; Jeon, In

    1996-03-01

    This report is to describe the concepts, operation status and user's manuals of nuclear materials accounting system which was developed to not only make out, report and manage the IAEA accounting reports but also maintain the accounting information. Therefore, facility operator could effectively make use of the accounting system without a special training by using this report. 3 tabs., 15 figs., (Author) .new

  6. National Waste Terminal Storage Program, planning and control system manual

    International Nuclear Information System (INIS)

    1976-09-01

    This manual contains a brief description of the NWTS program in order to define the environment within which the system must function; an overview of the system, and the concepts and techniques that were utilized in its development; and OWI implementation on the NWTS Program

  7. Sandia National Laboratories, California Environmental Management System program manual.

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2013-04-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

  8. SNL/CA Environmental Management System Program Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2005-09-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program was developed in accordance with Department of Energy (DOE) Order 450.1 and incorporates the elements of the International Standard on Environmental Management Systems, ISO 14001.

  9. Sandia National Laboratories, California Environmental Management System program manual

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2014-04-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

  10. MULTIPLE PROJECTIONS SYSTEM (MPS) - USER'S MANUAL VERSION 1.0

    Science.gov (United States)

    The report is a user's manual for version 1.0 of the Multiple Projections Systems (MPS), a computer system that can perform "what if" scenario analysis and report the final results (i.e., Rate of Further Progress - ROP - inventories) to EPA (i.e., the Aerometric Information Retri...

  11. Operation and maintenance manual for data acquisition system of MIDAS

    International Nuclear Information System (INIS)

    Lee, D. Y.; Park, W. M.; Kim, J. T.; Euh, D. J.

    2001-09-01

    This report describes an operation and maintenance manual of the data acquisition system and the data processing system for the DVI performance evaluation facility, MIDAS. The data acquisition system is implemented with VXI based system of Kinetic Systems TM , and the data processing PC. This report presents the configuration method and operation procedure for the operator. The modification procedure and method for functional extension and performance modification are also included for the future demand

  12. HDM/PASCAL Verification System User's Manual

    Science.gov (United States)

    Hare, D.

    1983-01-01

    The HDM/Pascal verification system is a tool for proving the correctness of programs written in PASCAL and specified in the Hierarchical Development Methodology (HDM). This document assumes an understanding of PASCAL, HDM, program verification, and the STP system. The steps toward verification which this tool provides are parsing programs and specifications, checking the static semantics, and generating verification conditions. Some support functions are provided such as maintaining a data base, status management, and editing. The system runs under the TOPS-20 and TENEX operating systems and is written in INTERLISP. However, no knowledge is assumed of these operating systems or of INTERLISP. The system requires three executable files, HDMVCG, PARSE, and STP. Optionally, the editor EMACS should be on the system in order for the editor to work. The file HDMVCG is invoked to run the system. The files PARSE and STP are used as lower forks to perform the functions of parsing and proving.

  13. Material control system simulator program reference manual

    Energy Technology Data Exchange (ETDEWEB)

    Hollstien, R.B.

    1978-01-24

    A description is presented of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts. Although MCSS may be used independently in the design or analysis of material handling and processing systems, it has been tailored toward the determination of material accountability and the response of material control systems to adversary action sequences.

  14. Material control system simulator program reference manual

    International Nuclear Information System (INIS)

    Hollstien, R.B.

    1978-01-01

    A description is presented of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts. Although MCSS may be used independently in the design or analysis of material handling and processing systems, it has been tailored toward the determination of material accountability and the response of material control systems to adversary action sequences

  15. Surface Moisture Measurement System Operation and Maintenance Manual

    International Nuclear Information System (INIS)

    Ritter, G.A.; Pearce, K.L.; Stokes, T.L.

    1995-12-01

    This operations and maintenance manual addresses deployment, equipment and field hazards, operating instructions, calibration verification, removal, maintenance, and other pertinent information necessary to safely operate and store the Surface Moisture Measurement System (SMMS) and Liquid Observation Well Moisture Measurement System (LOWMMS). These systems were developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks

  16. Management Information System Project. Data Processors Manual to the Program Oriented Accounting System: The Budgetary Process.

    Science.gov (United States)

    Foley, Walter; Harr, Gordon

    The purpose of this manual is to serve the needs of a data processing facility in the operation of a management information system (MIS). Included in the manual are system flowcharts, job control language, and system documentation. The system has been field tested and operates under IBM System 360/Model 65-05-MVT-HASP. The programing language is…

  17. XTAL system of crystallographic programs: programmer's manual

    International Nuclear Information System (INIS)

    Hall, S.R.; Stewart, J.M.; Norden, A.P.; Munn, R.J.; Freer, S.T.

    1980-02-01

    This document establishes the basis for collaborative writing of transportable computer programs for x-ray crystallography. The concepts and general-purpose utility subroutines described here can be readily adapted to other scientific calculations. The complete system of crystallographic programs and subroutines is called XTAL and replaces the XRAY (6,7,8) system of programs. The coding language for the XTAL system is RATMAC (5). The XTAL system of programs contains routines for controlling execution of application programs. In this sense it forms a suboperating system that presents the same computational environment to the user and programmer irrespective of the operating system in use at a particular installation. These control routines replace all FORTRAN I/O code, supply character reading and writing, supply binary file reading and writing, serve as a support library for applications programs, and provide for interprogram communication

  18. Material control system simulator user's manual

    International Nuclear Information System (INIS)

    Hollstien, R.B.

    1978-01-01

    This report describes the use of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts

  19. NASA work unit system file maintenance manual

    Science.gov (United States)

    1972-01-01

    The NASA Work Unit System is a management information system for research tasks (i.e., work units) performed under NASA grants and contracts. It supplies profiles on research efforts and statistics on fund distribution. The file maintenance operator can add, delete and change records at a remote terminal or can submit punched cards to the computer room for batch update. The system is designed for file maintenance by a person with little or no knowledge of data processing techniques.

  20. Infrastructure Management Information System User Manual

    Science.gov (United States)

    1998-10-01

    This publication describes and explains the user interface for the Infrastructure Management Information System (IMIS). The IMIS is designed to answer questions regarding public water supply, wastewater treatment, and census information. This publica...

  1. Cuerpo de Paz Manual de Sistema de Programacion y Capacitacion (Peace Corps Programming and Training System Manual): T0063.

    Science.gov (United States)

    Peace Corps, Washington, DC.

    This Spanish version of the Peace Corps Programming and Training System Manual is designed to help field staff members of the Peace Corps train volunteers. Its task descriptions, guidelines, examples, and definitions are intended to be practical and informative rather than restrictive. The manual is divided into six major sections: (1)…

  2. Manually operated small envelope scanner system

    Energy Technology Data Exchange (ETDEWEB)

    Sword, Charles Keith

    2017-04-18

    A scanner system and method for acquisition of position-based ultrasonic inspection data are described. The scanner system includes an inspection probe and a first non-contact linear encoder having a first sensor and a first scale to track inspection probe position. The first sensor is positioned to maintain a continuous non-contact interface between the first sensor and the first scale and to maintain a continuous alignment of the first sensor with the inspection probe. The scanner system may be used to acquire two-dimensional inspection probe position data by including a second non-contact linear encoder having a second sensor and a second scale, the second sensor positioned to maintain a continuous non-contact interface between the second sensor and the second scale and to maintain a continuous alignment of the second sensor with the first sensor.

  3. The JOSHUA (J80) system programmer`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Smetana, A.O.; McCort, J.T.; Westmoreland, B.W.

    1993-08-01

    The JOSHUA system routines (JS routines) can be used to manage a JOSHUA data base and execute JOSHUA modules on VAX/VMS and IBM/MVS computer systems. This manual provides instructions for using the JS routines and information about the internal data structures and logic used by the routines. It is intended for use primarily by JOSHUA systems programmers, however, advanced applications programmers may also find it useful. The JS routines are, as far as possible, written in ANSI FORTRAN 77 so that they are easily maintainable and easily portable to different computer systems. Nevertheless, the JOSHUA system provides features that are not available in ANSI FORTRAN 77, notably dynamic module execution and a data base of named, variable length, unformatted records, so some parts of the routines are coded in nonstandard FORTRAN or assembler (as a last resort). In most cases, the nonstandard sections of code are different for each computer system. To make it easy for programmers using the JS routines to avoid naming conflicts, the JS routines and common block all have six character names that begin with the characters {open_quotes}JS.{close_quotes} Before using this manual, one should be familiar with the JOSHUA system as described in {open_quotes}The JOSHUA Users` Manual,{close_quotes} ANSI FORTRAN 77, and at least one of the computer systems for which the JS routines have been implemented.

  4. Solvent Handbook Database System user's manual

    International Nuclear Information System (INIS)

    1993-03-01

    Industrial solvents and cleaners are used in maintenance facilities to remove wax, grease, oil, carbon, machining fluids, solder fluxes, mold release, and various other contaminants from parts, and to prepare the surface of various metals. However, because of growing environmental and worker-safety concerns, government regulations have already excluded the use of some chemicals and have restricted the use of halogenated hydrocarbons because they affect the ozone layer and may cause cancer. The Solvent Handbook Database System lets you view information on solvents and cleaners, including test results on cleaning performance, air emissions, recycling and recovery, corrosion, and non-metals compatibility. Company and product safety information is also available

  5. SNL/CA Environmental Management System Program Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2007-04-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004. Elements of the ISO standard overlap with those of Department of Energy (DOE) Order 450.1, thus SNL/CA's EMS program also meets the DOE requirements.

  6. 46 CFR 112.01-5 - Manual emergency lighting and power system.

    Science.gov (United States)

    2010-10-01

    ... EMERGENCY LIGHTING AND POWER SYSTEMS Definitions of Emergency Lighting and Power Systems § 112.01-5 Manual emergency lighting and power system. A manual emergency lighting and power system is one in which a single... 46 Shipping 4 2010-10-01 2010-10-01 false Manual emergency lighting and power system. 112.01-5...

  7. Integration of a browser based operator manual in the system environment of a process computer system

    International Nuclear Information System (INIS)

    Weber, Andreas; Erfle, Robert; Feinkohl, Dirk

    2012-01-01

    The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

  8. The development of nuclear material accountability system - software user's manual

    International Nuclear Information System (INIS)

    Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

    1999-07-01

    We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig

  9. A manual of recommended practices for hydrogen energy systems

    Energy Technology Data Exchange (ETDEWEB)

    Hoagland, W.; Leach, S. [W. Hoagland and Associates, Boulder, CO (United States)

    1997-12-31

    Technologies for the production, distribution, and use of hydrogen are rapidly maturing and the number and size of demonstration programs designed to showcase emerging hydrogen energy systems is expanding. The success of these programs is key to hydrogen commercialization. Currently there is no comprehensive set of widely-accepted codes or standards covering the installation and operation of hydrogen energy systems. This lack of codes or standards is a major obstacle to future hydrogen demonstrations in obtaining the requisite licenses, permits, insurance, and public acceptance. In a project begun in late 1996 to address this problem, W. Hoagland and Associates has been developing a Manual of Recommended Practices for Hydrogen Systems intended to serve as an interim document for the design and operation of hydrogen demonstration projects. It will also serve as a starting point for some of the needed standard-setting processes. The Manual will include design guidelines for hydrogen procedures, case studies of experience at existing hydrogen demonstration projects, a bibliography of information sources, and a compilation of suppliers of hydrogen equipment and hardware. Following extensive professional review, final publication will occur later in 1997. The primary goal is to develop a draft document in the shortest possible time frame. To accomplish this, the input and guidance of technology developers, industrial organizations, government R and D and regulatory organizations and others will be sought to define the organization and content of the draft Manual, gather and evaluate available information, develop a draft document, coordinate reviews and revisions, and develop recommendations for publication, distribution, and update of the final document. The workshop, Development of a Manual of Recommended Practices for Hydrogen Energy Systems, conducted on March 11, 1997 in Alexandria, Virginia, was a first step.

  10. 22 CFR 308.10 - Security of records systems-manual and automated.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Security of records systems-manual and automated... Security of records systems—manual and automated. The head of the agency has the responsibility of... destruction of manual and automatic record systems. These security safeguards shall apply to all systems in...

  11. Energy management information systems - planning manual and tool

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    An Energy Management Information System (EMIS) provides relevant information that makes energy, performance visible to various levels of an organization, enabling individuals and departments to plan, make decisions and take effective action to manage energy. This manual has two objectives: 1. To enable companies to conduct EMIS audits and prepare EMIS implementation plans; 2. To provide companies with the tools to prepare a financial business case for EMIS implementation. This manual consists of four parts: 1. EMIS Audit is theoretical and provides the methodology to be used by outside or in-house engineers and consultants to do a thorough EMIS Audit. 2. Implementation Plan is to help industry do the work themselves. 3. Appendices is to help the user develop an EMIS Audit, gather data and score their company, prepare a conceptual and detailed design, as well as a business and financial plan for implementation.

  12. Computerized low-level waste assay system operation manual

    International Nuclear Information System (INIS)

    Jones, D.F.; Cowder, L.R.; Martin, E.R.

    1976-01-01

    An operation and maintenance manual for the computerized low-level waste box counter is presented, which describes routine assay techniques as well as theory of operation treated in sufficient depth so that an experienced assayist can make nonroutine assays. In addition, complete system schematics are included, along with a complete circuit description to facilitate not only maintenance and troubleshooting, but also reproduction of the instrument if desired. Complete software system descriptions are included so far as calculational algorithms are concerned, although detailed instruction listings would have to be obtained from Group R-1 at LASL in order to make machine-language code changes

  13. A user's manual for managing database system of tensile property

    International Nuclear Information System (INIS)

    Ryu, Woo Seok; Park, S. J.; Kim, D. H.; Jun, I.

    2003-06-01

    This manual is written for the management and maintenance of the tensile database system for managing the tensile property test data. The data base constructed the data produced from tensile property test can increase the application of test results. Also, we can get easily the basic data from database when we prepare the new experiment and can produce better result by compare the previous data. To develop the database we must analyze and design carefully application and after that, we can offer the best quality to customers various requirements. The tensile database system was developed by internet method using Java, PL/SQL, JSP(Java Server Pages) tool

  14. Time warp operating system version 2.7 internals manual

    Science.gov (United States)

    1992-01-01

    The Time Warp Operating System (TWOS) is an implementation of the Time Warp synchronization method proposed by David Jefferson. In addition, it serves as an actual platform for running discrete event simulations. The code comprising TWOS can be divided into several different sections. TWOS typically relies on an existing operating system to furnish some very basic services. This existing operating system is referred to as the Base OS. The existing operating system varies depending on the hardware TWOS is running on. It is Unix on the Sun workstations, Chrysalis or Mach on the Butterfly, and Mercury on the Mark 3 Hypercube. The base OS could be an entirely new operating system, written to meet the special needs of TWOS, but, to this point, existing systems have been used instead. The base OS's used for TWOS on various platforms are not discussed in detail in this manual, as they are well covered in their own manuals. Appendix G discusses the interface between one such OS, Mach, and TWOS.

  15. Quality assurance manual for the development of digital systems

    International Nuclear Information System (INIS)

    Lee, Cheol Kwon; Kwon, Kee Choon; You, Young Eun; Kim, Kwan Hyun; Park, Jung Woo; Park, Chan Seok

    2001-12-01

    A digital safety system is being developed by three companies under the Korea Nuclear I and C System R and D Program. This Quality Assurance Manual (QAM) is written to ensure the safety and reliability of the system and to meet the regulatory requirements associated with quality assurance. This QAM describes eighteen elements of quality assurance criteria required for the development of the system, which are coincident with the criteria specified in Nuclear Energy Laws and Enforcement Regulations of Nuclear Energy Laws and 10CFR50 Appendix B. This QAM is submitted to the regulatory body with other documents related to the quality assurance activities performed during the system development. And its safety, validity and fulfillment are reviewed and audited in the review process of topical report of the digital safety system

  16. Can pulsed xenon ultraviolet light systems disinfect aerobic bacteria in the absence of manual disinfection?

    Science.gov (United States)

    Jinadatha, Chetan; Villamaria, Frank C; Ganachari-Mallappa, Nagaraja; Brown, Donna S; Liao, I-Chia; Stock, Eileen M; Copeland, Laurel A; Zeber, John E

    2015-04-01

    Whereas pulsed xenon-based ultraviolet light no-touch disinfection systems are being increasingly used for room disinfection after patient discharge with manual cleaning, their effectiveness in the absence of manual disinfection has not been previously evaluated. Our study indicates that pulsed xenon-based ultraviolet light systems effectively reduce aerobic bacteria in the absence of manual disinfection. These data are important for hospitals planning to adopt this technology as adjunct to routine manual disinfection. Published by Elsevier Inc.

  17. Operator's Manual for SHEBA Powered Tether Balloon System

    Science.gov (United States)

    Lappen, Cara-Lyn; Randall, David A.

    1998-01-01

    The Surface Heat and Energy Budget of the Arctic (SHEBA) was an intensive field project which took place in the Arctic Ocean from October 1997 through October 1998. Its purpose was to measure as many facets of the Arctic environment as possible so that we would be able to better understand the interaction between the ice, atmosphere, and ocean and their interactions with global climate. One aspect of the atmospheric field component was launching tethered balloons to monitor the profiles of temperature, wind, pressure, and humidity, as well as examine the vertical structure of cloud droplet sizes and distributions. The tethered balloon that we used was one specially designed for use in freezing climates by SPEC Corporation in Boulder, Colorado. A special winch that was able to withstand Arctic temperature and weather became necessary when the testing of simple winch systems used in warmer climates failed under these extreme conditions. The purpose of this manual is to acquaint any new user to the powered tethered balloon system deployed at the The Surface Heat and Energy Budget of the Arctic (SHEBA ice camp. It includes a description of the preparations necessary to get ready for a launch, the mechanics of the actual launch, and an account of the proper procedure for taking down the equipment when finished. It will also include tips on how to minimize potential equipment failures, some trouble shooting, and some safety ideas. This manual is designed so that new operators can use the system with minimal previous training. At the end of this manual, the reader will find a quick checklist.

  18. Data collection system. Volume 1, Overview and operators manual; Volume 2, Maintenance manual; Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Caudell, R.B.; Bauder, M.E.; Boyer, W.B.; French, R.E.; Isidoro, R.J.; Kaestner, P.C.; Perkins, W.G.

    1993-09-01

    Sandia National Laboratories (SNL) Instrumentation Development Department was tasked by the Defense Nuclear Agency (DNA) to record data on Tektronix RTD720 Digitizers on the HUNTERS TROPHY field test conducted at the Nevada Test Site (NTS) on September 18, 1992. This report contains a overview and description of the computer hardware and software that was used to acquire, reduce, and display the data. The document is divided into two volumes: an overview and operators manual (Volume 1) and a maintenance manual (Volume 2).

  19. User's manual for the reactor burnup system, REBUS

    International Nuclear Information System (INIS)

    Olson, A.P.; Regis, J.P.; Meneley, D.A.; Hoover, L.J.

    1972-01-01

    A user's manual for the REBUS System (REactor BUrnup System) is presented. Its primary purpose is to provide sufficient information about the REBUS capability to the user to ensure its efficient utilization. The current REBUS System either solves for the infinite time (equilibrium) operating conditions of a recycle system under fixed conditions, or solves for operating conditions during a single time step (non-equilibrium). The capability of studying various in-reactor fuel management and ex-reactor fuel management schemes has been included. REBUS has been operated with one- and two-dimensional diffusion theory neutronics solutions up to the present time. The model was specifically designed for extension to other neutronics models such as three-dimensional diffusion or transport theory and direct or synthesis solutions

  20. User's manual of JT-60 experimental data analysis system

    International Nuclear Information System (INIS)

    Hirayama, Takashi; Morishima, Soichi; Yoshioka, Yuji

    2010-02-01

    In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is a user's manual of the JT-60 experimental data analysis system. (author)

  1. Manual of program operation for data analysis from radiometer system

    International Nuclear Information System (INIS)

    Silva Mello, L.A.R. da; Migliora, C.G.S.

    1987-12-01

    This manual describes how to use the software to retrieve and analyse data from radiometer systems and raingauges used in the 12 GHz PROPAGATION MEASUREMENTS/CANADA - TELEBRAS COOPERATION PROGRAM. The data retrieval and analisys is being carried out by CETUC, as part of the activities of the project Simulacao de Enlaces Satelite (SES). The software for these tasks has been supplied by the Canadian Research Centre (CRC), together with the measurement equipment. The two following sections describe the use of the data retrieval routines and the data analysis routines of program ATTEN. Also, a quick reference guide for commands that can be used when a microcomputer is local or remotely connected to a radiometer indoor unit is included as a last section. A more detailed description of these commands, their objectives and cautions that should de taken when using them can be found in the manual ''12 GHz Propagation Measurements System - Volume 1 - Dual Slope Radiometer and Data Aquisition System'', supplied by Diversitel Communications Inc. (author) [pt

  2. Automated Transportation Management System (ATMS) user's manual. Revision 1

    International Nuclear Information System (INIS)

    Smith, P.D.

    1994-01-01

    The Automated Transportation Management System (ATMS) Software User Guide (SUG) constitutes the user procedures for the ATMS System. Information in this document will be used by the user to operate the automated system. It is intended to be used as a reference manual to guide and direct the user(s) through the ATMS software product and its environment. The objectives of ATMS are as follows: to better support the Procurement function with freight rate information; to free Transportation Logistics personnel from routine activities such as the auditing and input of freight billing information; to comply with Headquarters Department of Energy-Inspector General (DOE-IG) audit findings to automate transportation management functions; to reduce the keying of data into the Shipment Mobility Accountability Collection (SMAC) database; and to provide automation for the preparing of Bill of Lading, Declaration of Dangerous Goods, Emergency Response Guide and shipping Labels using HM181 Retrieval of hazardous material table text information

  3. Activity Management System user reference manual. Revision 1

    International Nuclear Information System (INIS)

    Gates, T.A.; Burdick, M.B.

    1994-01-01

    The Activity Management System (AMS) was developed in response to the need for a simple-to-use, low-cost, user interface system for collecting and logging Hanford Waste Vitrification Plant Project (HWVP) activities. This system needed to run on user workstations and provide common user access to a database stored on a local network file server. Most important, users wanted a system that provided a management tool that supported their individual process for completing activities. Existing system treated the performer as a tool of the system. All AMS data is maintained in encrypted format. Users can feel confident that any activities they have entered into the database are private and that, as the originator, they retain sole control over who can see them. Once entered into the AMS database, the activities cannot be accessed by anyone other than the originator, the designated agent, or by authorized viewers who have been explicitly granted the right to look at specific activities by the originator. This user guide is intended to assist new AMS users in learning how to use the application and, after the initial learning process, will serve as an ongoing reference for experienced users in performing infrequently used functions. Online help screens provide reference to some of the key information in this manual. Additional help screens, encompassing all the applicable material in this manual, will be incorporated into future AMS revisions. A third, and most important, source of help is the AMS administrator(s). This guide describes the initial production version of AMS, which has been designated Revision 1.0

  4. Safety handling manual for high dose rate remote afterloading system

    International Nuclear Information System (INIS)

    1999-01-01

    This manual is mainly for safety handling of 192 Ir-RALS (remote afterloading system) of high dose rate and followings were presented: Procedure and document format for the RALS therapy and for handling of its radiation source with the purpose of prevention of human errors and unexpected accidents, Procedure for preventing errors occurring in the treatment schedule and operation, and Procedure and format necessary for newly introducing the system into a facility. Consistency was intended in the description with the quality assurance guideline for therapy with small sealed radiation sources made by JASTRO (Japan Society for Therapeutic Radiology and Oncology). Use of the old type 60 Co-RALS was pointed out to be a serious problem remained and its safety handling procedure was also presented. (K.H.)

  5. Design manual of the wind power system; Furyoku hatsuden system no sekkei manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    For the purpose of contributing to the promotion/introduction of the wind power generation in Japan, systematical arrangement was made on items, standards/related laws, etc. to be considered upon designing the wind power system, further describing design examples of the standard system (case study). Out of the items necessary for the design, as to the investigation, arranged were matters and methods to be field-surveyed such as the site situation, surroundings, radio wave hindrance, noise hindrance, measurement, geology, etc. Concerning the determination of sizes of wind turbines to be introduced, procedures for setting sizes of wind turbines suitable for the places proposed for the installation were described. In the design, the knacks were summed up of designing wind power generation facilities, electric equipment, electric works, civil engineering, and measuring instrument. As to the working plan, indicated were the points to be taken notice of in the plan and the standard working process. Also shown were the evaluation method of economic efficiency, etc. In addition, the paper includes the related laws, system design examples, and the data attached. 10 refs., 13 figs., 59 tabs.

  6. Naturalistic driving observations of manual and visual-manual interactions with navigation systems and mobile phones while driving.

    NARCIS (Netherlands)

    Christoph, M. Nes, N. van & Knapper, A.

    2014-01-01

    This paper discusses a naturalistic driving study on the use of mobile phones and navigation systems while driving. Manual interactions with these devices while driving can cause distraction from the driving task and reduce traffic safety. In this study 21 subjects were observed for 5 weeks. Their

  7. PRIS-WEDAS. User’s Manual to the Web Enabled Data Acquisition System for PRIS

    International Nuclear Information System (INIS)

    2015-01-01

    The user manual for the Web Enabled Data Acquisition System (WEDAS), a system that supports the Power Reactor Information System (PRIS), provides instructions, guidelines and detailed definitions for each of the data items required for PRIS. The purpose of this manual is to ensure PRIS performance data are collected consistently and that the required quality of data collection is ensured. This PRIS-WEDAS user’s manual replaces reporting instructions published in the IAEA Technical Reports Series No. 428

  8. A manual low background alpha beta counting system

    Energy Technology Data Exchange (ETDEWEB)

    Levison, S; German, U; Peled, O; Turgeman, S; Vangrovitz, U; Tirosh, D; Piestum, S; Assido, H [Israel Atomic Energy Commission, Beersheba (Israel). Nuclear Research Center-Negev

    1996-12-01

    An Alpha and Beta counting system consisting of a micro controller-based electronic unit and detectors assembly was developed. The radiation detection unit consists of two proportional detectors (a main detector and a cosmic-ray guard detector) which can be easily disassembled for decontamination or repair. The detectors are mounted in a manual operating sample changer shielded by 5 cm of lead. Simplicity of maintenance and functional operation were taken into consideration in the design. The electronic unit supplies the high voltage and enables the operational functions including controls anti alarms. Calculations of net cpm of Alpha and Beta counting are displayed and can be printed. RS-232 communication option enables connection to a computer and operation of more sophisticated programs for calculations and data storage in the future (authors).

  9. A manual low background alpha beta counting system

    International Nuclear Information System (INIS)

    Levison, S.; German, U.; Peled, O.; Turgeman, S.; Vangrovitz, U.; Tirosh, D.; Piestum, S.; Assido, H.

    1996-01-01

    An Alpha and Beta counting system consisting of a micro controller-based electronic unit and detectors assembly was developed. The radiation detection unit consists of two proportional detectors (a main detector and a cosmic-ray guard detector) which can be easily disassembled for decontamination or repair. The detectors are mounted in a manual operating sample changer shielded by 5 cm of lead. Simplicity of maintenance and functional operation were taken into consideration in the design. The electronic unit supplies the high voltage and enables the operational functions including controls anti alarms. Calculations of net cpm of Alpha and Beta counting are displayed and can be printed. RS-232 communication option enables connection to a computer and operation of more sophisticated programs for calculations and data storage in the future (authors)

  10. The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    Juergen Kupitz

    2002-01-01

    This paper presents the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). It defines its rationale, key objectives and specifies the organizational structure. The IAEA General Conference (2000) has invited 'all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology' (GC(44)/RES/21) and invited Member States to consider to contribute to a task force on innovative nuclear reactors and fuel cycle (GC(44)/RES/22). In response to this invitation, the IAEA initiated an 'International Project on Innovative Nuclear Reactors and Fuel Cycles', INPRO. The Terms of Reference for INPRO were adopted at a preparatory meeting in November 2000, and the project was finally launched by the INPRO Steering Committee in May 2001. At the General Conference in 2001, first progress was reported, and the General Conference adopted a resolution on 'Agency Activities in the Development of Innovative Nuclear Technology' [GC(45)/RES/12, Tab F], giving INPRO a broad basis of support. The resolution recognized the 'unique role that the Agency can play in international collaboration in the nuclear field'. It invited both 'interested Member States to contribute to innovative nuclear technology activities' at the Agency as well as the Agency itself 'to continue it's efforts in these areas'. Additional endorsement came in a UN General Assembly resolution in December 2001 (UN GA 2001, A/RES/56/94), that again emphasized 'the unique role that the Agency can play in developing user requirements and in addressing safeguards, safety and environmental questions for innovative reactors and their fuel cycles' and stressed 'the need for international collaboration in the development of innovative nuclear technology'. As of February 2002, the following countries or entities have become members of INPRO: Argentina

  11. Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system

    International Nuclear Information System (INIS)

    Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

    1993-03-01

    The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data

  12. Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

    1993-03-01

    The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data.

  13. Wisconsin System for Instructional Management: Teachers' Manual for the Unified System. Practical Paper No. 18.

    Science.gov (United States)

    Bozeman, William C.; And Others

    Individualized instruction including continuous progress education and team teaching requires a complexity of organizational structure dissimilar to that of traditional schools. In such systems, teachers must maintain extensive and complex student record systems. This teachers' manual provides an example of a computerized record system developed…

  14. Guidance for the evaluation of innovative nuclear reactors and fuel cycles. Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2003-06-01

    technicians of the calibre and size needed to support a truly substantial nuclear contribution to global energy supplies. To set out the boundary conditions for the desired innovations of nuclear energy systems, INPRO established several task groups to define: Prospects and Potentials of nuclear power within the next 50 years; User Requirements for innovative nuclear energy systems (INS) in the area of Economics, Sustainability and Environment, Safety, Waste Management, Proliferation Resistance, and Cross Cutting Issues; and Methodology for Assessment of INS. Having completed these tasks, it is planned that several Member States will apply the INPRO methodology to make a judgement on the potential of INS under consideration for development, to specify corresponding research, development and demonstration (RD and D) needs for their development, and to identify improvements in the methodology. The results achieved as of the end of April 2003 (Phase 1A) are presented in this report. It is intended to issue separately the working material on which this report is based and which was produced at a number of consultancy meetings held during the course of the Project

  15. CAISSE (Computer Aided Information System on Solar Energy) technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Cantelon, P E; Beinhauer, F W

    1979-01-01

    The Computer Aided Information System on Solar Energy (CAISSE) was developed to provide the general public with information on solar energy and its potential uses and costs for domestic consumption. CAISSE is an interactive computing system which illustrates solar heating concepts through the use of 35 mm slides, text displays on a screen and a printed report. The user communicates with the computer by responding to questions about his home and heating requirements through a touch sensitive screen. The CAISSE system contains a solar heating simulation model which calculates the heating load capable of being supplied by a solar heating system and uses this information to illustrate installation costs, fuel savings and a 20 year life-cycle analysis of cost and benefits. The system contains several sets of radiation and weather data for Canada and USA. The selection of one of four collector models is based upon the requirements input during the computer session. Optimistic and pessimistic fuel cost forecasts are made for oil, natural gas, electricity, or propane; and the forecasted fuel cost is made the basis of the life cycle cost evaluation for the solar heating application chosen. This manual is organized so that each section describes one major aspect of the use of solar energy systems to provide energy for domestic consumption. The sources of data and technical information and the method of incorporating them into the CAISSE display system are described in the same order as the computer processing. Each section concludes with a list of future developments that could be included to make CAISSE outputs more regionally specific and more useful to designers. 19 refs., 1 tab.

  16. Standard Hydrogen Monitoring System-C operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The primary function of the SHMS-C is to monitor specifically for hydrogen in the waste tank vapor space which may also contain (but not be limited to) unknown quantities of air, nitrous oxide (N 2 O), ammonia (NH 3 ), water vapor, carbon dioxide (CO 2 ), carbon monoxide (CO) and other gaseous constituents. An electronically controlled grab sampler has replaced the manually operated sample system that was used in the original SHMS enclosure. Samples can now be operator or automatically initiated. Automatic initiation occurs based on the high hydrogen alarm level. Once a sample is obtained it is removed from the sampler and transported to a laboratory for analysis. This system is used to identify other gaseous constituents which are not measured by the hydrogen monitor. The design does not include any remote data acquisition or remote data logging equipment but provides a 4--20 mA dc process signals, and discrete alarm contacts, that can be utilized for remote data logging and alarming when desired. The SHMS-C arrangement consists of design modifications (piping, valves, filters, supports) to the SHMS-B arrangement necessary for the installation of a dual column gas chromatograph and associated sample and calibration gas lines. The gas chromatograph will provide real time, analytical quality, specific hydrogen measurements in low and medium range concentrations. The system is designed to sample process gases that are classified by NEC code as Class 1, Division 1, Group B

  17. EXPOSURE ANALYSIS MODELING SYSTEM (EXAMS): USER MANUAL AND SYSTEM DOCUMENTATION

    Science.gov (United States)

    The Exposure Analysis Modeling System, first published in 1982 (EPA-600/3-82-023), provides interactive computer software for formulating aquatic ecosystem models and rapidly evaluating the fate, transport, and exposure concentrations of synthetic organic chemicals - pesticides, ...

  18. Manual signs as augmentative and alternative communication system. Review article

    Directory of Open Access Journals (Sweden)

    Fàtima Vega Llobera

    2014-06-01

    Full Text Available There is a long tradition of scientific evidence about using hand signals simultaneously with oral language to promote the development of communication and language in children with or without disabilities. This article aims to review and analyze intervention work focused on the use of manual signs as augmentative communication system (AAC in hearing participants. Several criteria were used to narrow the search, selection, coding and synthesis of the 50 original scientific papers have finally been part of the review. The included studies were edited from 1970 to the present, at a national and international level and were published in English and Spanish. The bibliographic compilation was performed through searches by keyword in bibliographic databases, with the help of search engines (Google Scholar and through secondary searches. From each of the scientific articles the following data was extracted: year of the study, the country of origin, the characteristics of the participants, the design and the methodology and the obtained results. This information has been analyzed and compared. The results of the study highlight that, despite the diversity in results, the signing use as augmentative communication system is effective to improve language development, receptive and expressive level.

  19. Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2009-09-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO project and an evaluation of existing and future reactor designs the publication covers nuclear fuel cycle issues in detail. It is expected that this documentation will provide IAEA Member States and their nuclear engineers and designers, as well as policy makers with useful information on status and trends of future nuclear fuel cycle technologies. Due to the size of the full report it was decided to create a summary of the information and attach a CD-ROM in the back of this summary report with the full text of the report

  20. Dairy Analytics and Nutrient Analysis (DANA) Prototype System User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Sam Alessi; Dennis Keiser

    2012-10-01

    This document is a user manual for the Dairy Analytics and Nutrient Analysis (DANA) model. DANA provides an analysis of dairy anaerobic digestion technology and allows users to calculate biogas production, co-product valuation, capital costs, expenses, revenue and financial metrics, for user customizable scenarios, dairy and digester types. The model provides results for three anaerobic digester types; Covered Lagoons, Modified Plug Flow, and Complete Mix, and three main energy production technologies; electricity generation, renewable natural gas generation, and compressed natural gas generation. Additional options include different dairy types, bedding types, backend treatment type as well as numerous production, and economic parameters. DANA’s goal is to extend the National Market Value of Anaerobic Digester Products analysis (informa economics, 2012; Innovation Center, 2011) to include a greater and more flexible set of regional digester scenarios and to provide a modular framework for creation of a tool to support farmer and investor needs. Users can set up scenarios from combinations of existing parameters or add new parameters, run the model and view a variety of reports, charts and tables that are automatically produced and delivered over the web interface. DANA is based in the INL’s analysis architecture entitled Generalized Environment for Modeling Systems (GEMS) , which offers extensive collaboration, analysis, and integration opportunities and greatly speeds the ability construct highly scalable web delivered user-oriented decision tools. DANA’s approach uses server-based data processing and web-based user interfaces, rather a client-based spreadsheet approach. This offers a number of benefits over the client-based approach. Server processing and storage can scale up to handle a very large number of scenarios, so that analysis of county, even field level, across the whole U.S., can be performed. Server based databases allow dairy and digester

  1. AutoBayes Program Synthesis System Users Manual

    Science.gov (United States)

    Schumann, Johann; Jafari, Hamed; Pressburger, Tom; Denney, Ewen; Buntine, Wray; Fischer, Bernd

    2008-01-01

    Program synthesis is the systematic, automatic construction of efficient executable code from high-level declarative specifications. AutoBayes is a fully automatic program synthesis system for the statistical data analysis domain; in particular, it solves parameter estimation problems. It has seen many successful applications at NASA and is currently being used, for example, to analyze simulation results for Orion. The input to AutoBayes is a concise description of a data analysis problem composed of a parameterized statistical model and a goal that is a probability term involving parameters and input data. The output is optimized and fully documented C/C++ code computing the values for those parameters that maximize the probability term. AutoBayes can solve many subproblems symbolically rather than having to rely on numeric approximation algorithms, thus yielding effective, efficient, and compact code. Statistical analysis is faster and more reliable, because effort can be focused on model development and validation rather than manual development of solution algorithms and code.

  2. Sandia National Laboratories, California Environmental Management System Program Manual.

    Energy Technology Data Exchange (ETDEWEB)

    2009-04-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 450.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site received ISO 14001 certification in September 2006. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy Management and Fleet Services Environmental programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has several groups operating at Sandia

  3. Sandia National Laboratories, California Environmental Management System program manual.

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2012-03-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004and Department of Energy (DOE) Order 436.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site first received ISO 14001 certification in September 2006 and recertification in 2009. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy and Water Resource Management and Fleet Services programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has

  4. Sandia National Laboratories, California Environmental Management System Program Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Barbara L.

    2011-04-01

    The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004and Department of Energy (DOE) Order 450.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site received ISO 14001 certification in September 2006. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy Management and Fleet Services programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has several groups operating at Sandia National Laboratories

  5. Physical habitat simulation system reference manual: version II

    Science.gov (United States)

    Milhous, Robert T.; Updike, Marlys A.; Schneider, Diane M.

    1989-01-01

    stream system basis. Such analysis is outside the scope of this manual, which concentrates on simulation of physical habitat based on depth, velocity, and a channel index. The results form PHABSIM can be used alone or by using a series of habitat time series programs that have been developed to generate monthly or daily habitat time series from the Weighted Usable Area versus streamflow table resulting from the habitat simulation programs and streamflow time series data. Monthly and daily streamflow time series may be obtained from USGS gages near the study site or as the output of river system management models.

  6. HORECA. Hoger onderwijs reactor elementary core analysis system. User's manual

    International Nuclear Information System (INIS)

    Battum, E. van; Serov, I.V.

    1993-07-01

    HORECA is developed at IRI Delft for quick analysis of power distribution, burnup and safety for the HOR. It can be used for the manual search of a better loading of the reactor. HORECA is based on the Penn State Fuel Management Package and uses the MCRAC code included in this package as a calculation engine. (orig./HP)

  7. The IAEA's international project on innovative nuclear reactors and fuel cycles (INPRO)

    International Nuclear Information System (INIS)

    Kuptiz, Juergen; )

    2002-01-01

    This paper presents the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). It defines its rationale, key objectives and specifies the organizational structure. The IAEA General Conference (2000) has invited all interested Member states to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology and invited Member states to consider to contribute to a task force on innovative nuclear reactors and fuel cycle

  8. User's manual for the Graphical Constituent Loading Analysis System (GCLAS)

    Science.gov (United States)

    Koltun, G.F.; Eberle, Michael; Gray, J.R.; Glysson, G.D.

    2006-01-01

    This manual describes the Graphical Constituent Loading Analysis System (GCLAS), an interactive cross-platform program for computing the mass (load) and average concentration of a constituent that is transported in stream water over a period of time. GCLAS computes loads as a function of an equal-interval streamflow time series and an equal- or unequal-interval time series of constituent concentrations. The constituent-concentration time series may be composed of measured concentrations or a combination of measured and estimated concentrations. GCLAS is not intended for use in situations where concentration data (or an appropriate surrogate) are collected infrequently or where an appreciable amount of the concentration values are censored. It is assumed that the constituent-concentration time series used by GCLAS adequately represents the true time-varying concentration. Commonly, measured constituent concentrations are collected at a frequency that is less than ideal (from a load-computation standpoint), so estimated concentrations must be inserted in the time series to better approximate the expected chemograph. GCLAS provides tools to facilitate estimation and entry of instantaneous concentrations for that purpose. Water-quality samples collected for load computation frequently are collected in a single vertical or at single point in a stream cross section. Several factors, some of which may vary as a function of time and (or) streamflow, can affect whether the sample concentrations are representative of the mean concentration in the cross section. GCLAS provides tools to aid the analyst in assessing whether concentrations in samples collected in a single vertical or at single point in a stream cross section exhibit systematic bias with respect to the mean concentrations. In cases where bias is evident, the analyst can construct coefficient relations in GCLAS to reduce or eliminate the observed bias. GCLAS can export load and concentration data in formats

  9. Instruction manual for operating the Sensys System for temporary traffic counts

    Science.gov (United States)

    2010-01-01

    This instruction manual provides information and the procedures for using the Sensys System, which was initially designed to operate in a server controlled network, for temporary traffic counts. The instructions will allow the user to fully understan...

  10. Computer program user's manual for FIREFINDER digital topographic data verification library dubbing system

    Science.gov (United States)

    Ceres, M.; Heselton, L. R., III

    1981-11-01

    This manual describes the computer programs for the FIREFINDER Digital Topographic Data Verification-Library-Dubbing System (FFDTDVLDS), and will assist in the maintenance of these programs. The manual contains detailed flow diagrams and associated descriptions for each computer program routine and subroutine. Complete computer program listings are also included. This information should be used when changes are made in the computer programs. The operating system has been designed to minimize operator intervention.

  11. Manual Therapy

    OpenAIRE

    Hakgüder, Aral; Kokino, Siranuş

    2002-01-01

    Manual therapy has been used in the treatment of pain and dysfunction of spinal and peripheral joints for more than a hundred years. Manual medicine includes manipulation, mobilization, and postisometric relaxation techniques. The aim of manual therapy is to enhance restricted movement caused by blockage of joints keeping postural balance, restore function and maintain optimal body mechanics. Anatomic, biomechanical, and neurophysiological evaluations of the leucomotor system is essential for...

  12. Quality Manual

    Science.gov (United States)

    Koch, Michael

    The quality manual is the “heart” of every management system related to quality. Quality assurance in analytical laboratories is most frequently linked with ISO/IEC 17025, which lists the standard requirements for a quality manual. In this chapter examples are used to demonstrate, how these requirements can be met. But, certainly, there are many other ways to do this.

  13. A training manual for event history data management using Health and Demographic Surveillance System data.

    Science.gov (United States)

    Bocquier, Philippe; Ginsburg, Carren; Herbst, Kobus; Sankoh, Osman; Collinson, Mark A

    2017-06-26

    The objective of this research note is to introduce a training manual for event history data management. The manual provides a first comprehensive guide to longitudinal Health and Demographic Surveillance System (HDSS) data management that allows for a step-by-step description of the process of structuring and preparing a dataset for the calculation of demographic rates and event history analysis. The research note provides some background information on the INDEPTH Network, and the iShare data repository and describes the need for a manual to guide users as to how to correctly handle HDSS datasets. The approach outlined in the manual is flexible and can be applied to other longitudinal data sources. It facilitates the development of standardised longitudinal data management and harmonization of datasets to produce a comparative set of results.

  14. Results of INPRO in the area of economics

    International Nuclear Information System (INIS)

    Depisch, F.; Kupitz, J.

    2004-01-01

    The intergovernmental panel on climate change (IPCC) had developed scenarios for future energy needs that were documented in a special report on emissions scenarios, these scenarios show a wide range of possible energy demand reflecting uncertainties in the future. In this paper the impact of 4 selected scenarios on nuclear power development is described. The important message is that nuclear technology must benefit more from feedback experience and learning than any other energy source to stay competitive. 2 basic economic principles emerge: 1) the cost of energy from innovative nuclear energy systems, taking all costs and credits into account must be competitive with that of alternative energy sources, and 2) innovative nuclear energy systems must represent an attractive investment compared with other major capital investments. To be cost competitive, cost reductions are required in capital costs, operating and maintenance cost, fuel costs and in total unit energy costs. Achieving such cost reduction will contribute to investor confidence. (A.C.)

  15. 100-N technical manual. Volume 2A: Systems descriptions

    Energy Technology Data Exchange (ETDEWEB)

    1963-12-31

    This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.

  16. Tubular wells perforation manual for investigation and training of Guarani Aquifer System

    International Nuclear Information System (INIS)

    2007-01-01

    The Environmental protection and sustainable development of the Aquifer Guarani System project is a initiative by Argentina, Brasil, Paraguay y Uruguay with the aim to raise the knowledge, legal and institutional sustainable management from 2003-2008 period. The Guarani consortium integrated by Tahal Engineers Ltda.(Israel), SEINCO SRL. (Uruguay), Hidrocontrol S:A:(Paraguay), Arcadis Hidroambiente S.A. (Argentina) have shown in Tubular wells perforation for investigation and training of Guarani Aquifer System manual their first product. This Manual includes technical especifications focused in Guarani Aquifer System harmessing building

  17. Composting of tobacco plant waste by manual turning and forced aeration system

    OpenAIRE

    Nonglak Saithep

    2009-01-01

    The efficiency of tobacco plant waste composting, by the manual turning and the forced aeration system, was compared. Tobacco plant waste, cow manure, urea fertiliser, and a compost inoculum mixture at a 100:10:0.2:0.01 ratio respectively, with 60% (w/v) moisture content, were set up in piling forms. The piles of the manual turning system were provided with turning aeration by hand at intervals of 7 days during the composting process. For the forced aeration system, each pile was aerated by a...

  18. Composting of tobacco plant waste by manual turning and forced aeration system

    Directory of Open Access Journals (Sweden)

    Nonglak Saithep

    2009-05-01

    Full Text Available The efficiency of tobacco plant waste composting, by the manual turning and the forced aeration system, was compared. Tobacco plant waste, cow manure, urea fertiliser, and a compost inoculum mixture at a 100:10:0.2:0.01 ratio respectively, with 60% (w/v moisture content, were set up in piling forms. The piles of the manual turning system were provided with turning aeration by hand at intervals of 7 days during the composting process. For the forced aeration system, each pile was aerated by a 3-HP air pump with a flow rate of 19 litres min-1 for 15 minutes every morning and evening. The completely randomised design of turned and force-aerated piles was performed in triplicate. The composting activity of both systems during the composting period was measured by several parameters: temperature, pH, moisture content, C/N ratio, growth of microorganisms, cellulase activity, and nicotine degradation in the set-up piles. Both systems had similar temperature, pH, and moisture content conditions in the piles during the composting process. However, the forced aeration system was more advantageous for the growth of mesophilic and thermophilic microorganisms, for cellulase activity from cellulase-producing microorganisms, and for nicotine degradation, when compared to the manual turning system. In conclusion, the forced aeration system was more efficient than the manual turning system in composting and is a viable alternative method for the composting process.

  19. The influence of image setting on intracranial translucency measurement by manual and semi-automated system.

    Science.gov (United States)

    Zhen, Li; Yang, Xin; Ting, Yuen Ha; Chen, Min; Leung, Tak Yeung

    2013-09-01

    To investigate the agreement between manual and semi-automated system and the effect of different image settings on intracranial translucency (IT) measurement. A prospective study was conducted on 55 women carrying singleton pregnancy who attended first trimester Down syndrome screening. IT was measured both manually and by semi-automated system at the same default image setting. The IT measurements were then repeated with the post-processing changes in the image setting one at a time. The difference in IT measurements between the altered and the original images were assessed. Intracranial translucency was successfully measured on 55 images both manually and by semi-automated method. There was strong agreement in IT measurements between the two methods with a mean difference (manual minus semi-automated) of 0.011 mm (95% confidence interval--0.052 mm-0.094 mm). There were statistically significant variations in both manual and semi-automated IT measurement after changing the Gain and the Contrast. The greatest changes occurred when the Contrast was reduced to 1 (IT reduced by 0.591 mm in semi-automated; 0.565 mm in manual), followed by when the Gain was increased to 15 (IT reduced by 0.424 mm in semi-automated; 0.524 mm in manual). The image settings may affect IT identification and measurement. Increased Gain and reduced Contrast are the most influential factors and may cause under-measurement of IT. © 2013 John Wiley & Sons, Ltd.

  20. Hanford Environmental Information System (HEIS) Operator`s Manual. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Schreck, R.I.

    1991-10-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. This manual describes the facilities available to the operational user who is responsible for data entry, processing, scheduling, reporting, and quality assurance. A companion manual, the HEIS User`s Manual, describes the facilities available-to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines.

  1. Acquisition and Development of System Command (SYSCOM) Technical Manuals

    National Research Council Canada - National Science Library

    2003-01-01

    ... (NAVSEA) and Space and Naval Warfare Systems Command (SPAWAR). TMs are the primary information source for technical training, installation, operation, testing, maintenance, and repair associated with NAVSEA/SPAWAR systems or equipment...

  2. Operations manual for the megachannel gamma-ray coincidence system

    International Nuclear Information System (INIS)

    Ruhter, W.

    1977-01-01

    To aid in the study of nuclear structures, a megachannel pulse-height coincidence analysis system on a PDP-8 computer was constructed. The system digitizes the energies of coincident gamma-rays and stores the resultant information on a moving-head disk. The system uses a minicomputer to sort and store gamma-gamma coincident information on line. The megachannel system and how to use it are described

  3. Radon-daughter chamber instrumentation system reference manual

    International Nuclear Information System (INIS)

    Showalter, R.; Johnson, L.

    1985-01-01

    The radon-daughter chamber instrumentation system collects environmental data from the radon-daughter chamber. These data are then recorded on a Tandberg system tape cartridge and transmitted to the HP-1000 computer for processing. Generators which inject radon and condensation nuclei into the chamber are also included with the instrumentation system

  4. Material control system simulator user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Hollstien, R.B.

    1978-01-24

    This report describes the use of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts.

  5. Design manual. [High temperature heat pump for heat recovery system

    Energy Technology Data Exchange (ETDEWEB)

    Burch, T.E.; Chancellor, P.D.; Dyer, D.F.; Maples, G.

    1980-01-01

    The design and performance of a waste heat recovery system which utilizes a high temperature heat pump and which is intended for use in those industries incorporating indirect drying processes are described. It is estimated that use of this heat recovery system in the paper, pulp, and textile industries in the US could save 3.9 x 10/sup 14/ Btu/yr. Information is included on over all and component design for the heat pump system, comparison of prime movers for powering the compressor, control equipment, and system economics. (LCL)

  6. Operators manual for a computer controlled impedance measurement system

    Science.gov (United States)

    Gordon, J.

    1987-02-01

    Operating instructions of a computer controlled impedance measurement system based in Hewlett Packard instrumentation are given. Hardware details, program listings, flowcharts and a practical application are included.

  7. Manual editing of automatically recorded data in an anesthesia information management system.

    Science.gov (United States)

    Wax, David B; Beilin, Yaakov; Hossain, Sabera; Lin, Hung-Mo; Reich, David L

    2008-11-01

    Anesthesia information management systems allow automatic recording of physiologic and anesthetic data. The authors investigated the prevalence of such data modification in an academic medical center. The authors queried their anesthesia information management system database of anesthetics performed in 2006 and tabulated the counts of data points for automatically recorded physiologic and anesthetic parameters as well as the subset of those data that were manually invalidated by clinicians (both with and without alternate values manually appended). Patient, practitioner, data source, and timing characteristics of recorded values were also extracted to determine their associations with editing of various parameters in the anesthesia information management system record. A total of 29,491 cases were analyzed, 19% of which had one or more data points manually invalidated. Among 58 attending anesthesiologists, each invalidated data in a median of 7% of their cases when working as a sole practitioner. A minority of invalidated values were manually appended with alternate values. Pulse rate, blood pressure, and pulse oximetry were the most commonly invalidated parameters. Data invalidation usually resulted in a decrease in parameter variance. Factors independently associated with invalidation included extreme physiologic values, American Society of Anesthesiologists physical status classification, emergency status, timing (phase of the procedure/anesthetic), presence of an intraarterial catheter, resident or certified registered nurse anesthetist involvement, and procedure duration. Editing of physiologic data automatically recorded in an anesthesia information management system is a common practice and results in decreased variability of intraoperative data. Further investigation may clarify the reasons for and consequences of this behavior.

  8. Manual for IRS Coding. Joint IAEA/NEA International Reporting System for Operating Experience

    International Nuclear Information System (INIS)

    2011-01-01

    The International Reporting System for Operating Experience (IRS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). In early 2010, the IAEA and OECD/NEA jointly issued the IRS Guidelines, which described the reporting system and process and gave users the necessary elements to enable them to produce IRS reports to a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. The purpose of the present Manual for IRS Coding is to provide supplementary guidance specifically on the coding element of IRS reports to ensure uniform coding of events that are reported through IRS. This Coding Manual does not supersede the IRS Guidelines, but rather, supports users and preparers in achieving a consistent and high level of quality in their IRS reports. Consistency and high quality in the IRS reports allow stakeholders to search and retrieve specific event information with ease. In addition, well-structured reports also enhance the efficient management of the IRS database. This Coding Manual will give specific guidance on the application of each section of the IRS codes, with examples where necessary, of when and how these codes are to be applied. As this reporting system is owned by the Member States, this manual has been developed and approved by the IRS National Coordinators with the assistance of the IAEA and NEA secretariats

  9. Manual and automatic locomotion scoring systems in dairy cows: A review

    NARCIS (Netherlands)

    Schlageter-Tello, A.; Bokkers, E.A.M.; Groot Koerkamp, P.W.G.; Hertem, van T.; Viazzi, S.; Romanini Bites, E.; Halachmi, I.; Bahr, C.; Berckmans, D.; Lokhorst, K.

    2014-01-01

    The objective of this review was to describe, compare and evaluate agreement, reliability, and validity of manual and automatic locomotion scoring systems (MLSSs and ALSSs, respectively) used in dairy cattle lameness research. There are many different types of MLSSs and ALSSs. Twenty-five MLSSs were

  10. Information Resources; A Searcher's Manual. MOREL Regional Information System for Educators.

    Science.gov (United States)

    Grimes, George; Doyle, James

    This document is one of a series describing the background, functions, and utilization of the Regional Information System (RIS) developed by the Michigan-Ohio Regional Educational Laboratory (MOREL). The purpose of this manual is to detail a procedure for performing a productive search of information resources which can satisfy the informational…

  11. Image-guided system versus manual marking for toric intraocular lens alignment in cataract surgery

    NARCIS (Netherlands)

    Webers, V.S.C.; Bauer, N.J.C.; Visser, N.; Berendschot, T.T.J.M.; van den Biggelaar, F.J.H.M.; Nuijts, R.M.M.A.

    2017-01-01

    Purpose To compare the accuracy of toric intraocular lens (IOL) alignment using the Verion Image-Guided System versus a conventional manual ink-marking procedure. Setting University Eye Clinic Maastricht, Maastricht, the Netherlands. Design Prospective randomized clinical trial. Methods Eyes with

  12. Manual for SFR R and D and Technology Monitoring System Administrator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

    2008-05-15

    This report is a administrator manual on R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. First of all, enterprise project management solution is introduced and then enterprise resources and data creation method are described. Also it made a description of project web assess design, data management method etc.

  13. Module type plant system dynamics analysis code (MSG-COPD). Code manual

    International Nuclear Information System (INIS)

    Sakai, Takaaki

    2002-11-01

    MSG-COPD is a module type plant system dynamics analysis code which involves a multi-dimensional thermal-hydraulics calculation module to analyze pool type of fast breeder reactors. Explanations of each module and the methods for the input data are described in this code manual. (author)

  14. STATE ACID RAIN RESEARCH AND SCREENING SYSTEM - VERSION 1.0 USER'S MANUAL

    Science.gov (United States)

    The report is a user's manual that describes Version 1.0 of EPA's STate Acid Rain Research and Screening System (STARRSS), developed to assist utility regulatory commissions in reviewing utility acid rain compliance plans. It is a screening tool that is based on scenario analysis...

  15. EDAS-manual. SATAN - system to analyze tremendous amounts of nuclear data. Vol. 2

    International Nuclear Information System (INIS)

    Goeringer, H.; Gralla, S.; Malzacher, P.; Richter, M.; Schall, D.; Winkelmann, K.

    1988-09-01

    The system to analyze tremendous amounts of nuclear data (SATAN) shows different steps of a special experiment data evaluation called 'Linearisation'. The report contains the EDAS-manual with EDAS-command, TSO-command, macro and procedure. Syntax and usage of EDAS macros are explained. (DG)

  16. Manual for SFR R and D and Technology Monitoring System Administrator

    International Nuclear Information System (INIS)

    Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

    2008-05-01

    This report is a administrator manual on R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. First of all, enterprise project management solution is introduced and then enterprise resources and data creation method are described. Also it made a description of project web assess design, data management method etc

  17. Standard Hydrogen Monitoring System-D operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standard Hydrogen Monitoring System-D (SHMS-D) used in the 200E and 200W area tank farms on the Hanford Site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. However, it does provide more information on the system than a Plant Operating Procedure. The intent here is that the system is started up by a technician or engineer who has completed tank farms training course No. 351405, and then the only actions performed by Operations will be routine log taking. If any problems not addressed by the operating procedure are encountered with the unit, engineering should be contacted

  18. Standard hydrogen monitoring system - E operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standard Hydrogen Monitoring System- E (SHMS-E) used in the 200E and 20OW area tank farms on the Hanford Site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. However, it does provide more information on the system than a Plant Operating Procedure. The intent here is that the system is started up by a technician or engineer who has completed tank farms training course for SHMS, and then the only actions performed by Operations will be routine log taking. If any problems not addressed by the operating procedure are encountered with the unit, engineering should be contacted

  19. User's manual of a support system for human reliability analysis

    International Nuclear Information System (INIS)

    Yokobayashi, Masao; Tamura, Kazuo.

    1995-10-01

    Many kinds of human reliability analysis (HRA) methods have been developed. However, users are required to be skillful so as to use them, and also required complicated works such as drawing event tree (ET) and calculation of uncertainty bounds. Moreover, each method is not so complete that only one method of them is not enough to evaluate human reliability. Therefore, a personal computer (PC) based support system for HRA has been developed to execute HRA practically and efficiently. The system consists of two methods, namely, simple method and detailed one. The former uses ASEP that is a simplified THERP-technique, and combined method of OAT and HRA-ET/DeBDA is used for the latter. Users can select a suitable method for their purpose. Human error probability (HEP) data were collected and a database of them was built to use for the support system. This paper describes outline of the HRA methods, support functions and user's guide of the system. (author)

  20. SDDOT'S enhanced pavement management system : visual distress survey manual [2017

    Science.gov (United States)

    2017-05-11

    In 1993, the South Dakota Department of Transportation initiated the Research Project SD93-14, Enhancement of South Dakotas Pavement Management System. As the Research Project progressed, it was determined that to better evaluate the condition of ...

  1. SIDA - System for importation distribution and acquisition of radioisotope - User manual

    International Nuclear Information System (INIS)

    1991-01-01

    The SIDA manual (system for importation, distribution and acquisition of radioisotopes) is presented. The SIDA is a system of consult and update to control importation and distribution of radioisotopes in the country. It allows to accompany processes from importation requirement to distribution of radioisotopes, executing the accountancy of I-125, which is distributed for several interprises. The system was developed in CLIPPER87 using DBASE III PLUS data base management. (M.C.K.)

  2. Standard hydrogen monitoring system-B operation and maintenance manual

    International Nuclear Information System (INIS)

    Bender, R.M.

    1995-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standards Hydrogen Monitoring System-B (SHMS-B) used in the 200E and 200W area tank farms on the Hanford site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. The primary function of the SHMS-B is to monitor specifically for hydrogen in the waste tank vapor space which may also contain unknown quantities of other gaseous constituents

  3. Flexible Receiver Radiation Detection System (FRRDS) Users Manual

    International Nuclear Information System (INIS)

    Troyer, G.L.

    1996-01-01

    The Flexible Receiver Radiation Detection System (FRRDS) comprises a control computer, a remote data acquisition subsystem, and three hyperpure germanium gamma radiation detectors. The scope of this document is the description of various steps for the orderly start-up, use, and shutdown of the FRRDS. Only those items necessary for these oprations are included. This document is a companion to WHC-SD-W151-UM-002, 'Operating Instructions for the 42 Inch Flexible Receiver,' WHC-SD-W151-UM-003, 'Operating Instructions for the 4-6 Inch Flexible Receiver,' and the vendor supplied system users guide (Ref. 6)

  4. MARS code manual volume I: code structure, system models, and solution methods

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Kim, Kyung Doo; Bae, Sung Won; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu; Yoon, Churl

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This theory manual provides a complete list of overall information of code structure and major function of MARS including code architecture, hydrodynamic model, heat structure, trip / control system and point reactor kinetics model. Therefore, this report would be very useful for the code users. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  5. The Army Communications Objectives Measurement System (ACOMS) Users’ Manual

    Science.gov (United States)

    1988-07-01

    and analysis system to support Army (1) assessments of advertising program effectiveness; (2) assessments of advertising strategy efficiencies; (3...advertising program effectiveness in a timely fashion; 2 (2) To support Army assessments of advertising strategy in an integrated framework; and (3...ACOMS data to assess the Army’s advertising strategy . ACOMS was designed to be used to examine the extent to which the Army’s intended messages are

  6. Computer Directed Training System (CDTS), User’s Manual

    Science.gov (United States)

    1983-07-01

    lessons, together with an estimate of the time required for completion. a. BSCOl0. This lesson in BASIC ( Beginners All Purpose Symbolic Instruction Code...A2-8 FIGURESj Figure A2-1. Training Systems Manager and Training Monitors Responsibility Flowchart ...training at the site. Therefore, the TSM must be knowledgeable in the various tasks required. Figure A2-1 illustrates the position in the flowchart . These

  7. Spent Fuel Test - Climax data acquisition system operations manual

    International Nuclear Information System (INIS)

    Nyholm, R.A.

    1983-01-01

    The Spent Fuel Test-Climax (SFT-C) is a test of the retrievable, deep geologic storage of commercially generated, spent nuclear reactor fuel in granite rock. Eleven spent fuel assemblies, together with 6 electrical simulators and 20 guard heaters, are emplaced 420 m below the surface in the Climax granite at the US Department of Energy Nevada Test Site. On June 2, 1978, Lawrence Livermore National Laboratory (LLNL) secured funding for the SFT-C, and completed spent fuel emplacement May 28, 1980. The multi-year duration test is located in a remote area and is unattended much of the time. An extensive array of radiological safety and geotechnical instrumentation is deployed to monitor the test performance. A dual minicomputer-based data acquisition system (DAS) collects and processes data from more than 900 analog instruments. This report documents the software element of the LLNL developed SFT-C Data Acquisition System. It defines the operating system and hardware interface configurations, the special applications software and data structures, and support software

  8. Standard manual reprocessing of angiographic systems in the hybrid OR

    Directory of Open Access Journals (Sweden)

    Buhl Sebastian

    2017-09-01

    Full Text Available A current FDA guidance demands the validation of cleaning and disinfecting protocols even for non-sterile medical devices. The aim of this work is to clarify whether this is already possible using the guidance itself as well as the German DIN EN ISO 17664. An angiography system (Artis Zeego / Pheno - Siemens was selected as a test object for the validation of a cleaning and disinfection protocol for medical devices in a hybrid operating room. In pilot study prior to the trial, critical points of the system were evaluated by means of questionnaires to clinical users (OTA, surgical technicians. An initial assessment of the in-house cleaning protocols used in the hospitals was done by using a fluorescence assay. The microbiological examination took place subsequently by contact plates and swabbing to determine the amount and type of germs on the surfaces of the system. These experiments were done at three different clinical sites. It was found that there was a significant germ count on several surfaces of the product even after in-house cleaning and disinfection (C&D. After application of an enhanced C&D plan, these germs could be greatly reduced at all verified sites. In addition, it could be shown that DIN EN ISO 17664 can in principle be applied to non-sterile medical products.

  9. Comparison of Inoculation with the InoqulA and WASP Automated Systems with Manual Inoculation

    Science.gov (United States)

    Croxatto, Antony; Dijkstra, Klaas; Prod'hom, Guy

    2015-01-01

    The quality of sample inoculation is critical for achieving an optimal yield of discrete colonies in both monomicrobial and polymicrobial samples to perform identification and antibiotic susceptibility testing. Consequently, we compared the performance between the InoqulA (BD Kiestra), the WASP (Copan), and manual inoculation methods. Defined mono- and polymicrobial samples of 4 bacterial species and cloudy urine specimens were inoculated on chromogenic agar by the InoqulA, the WASP, and manual methods. Images taken with ImagA (BD Kiestra) were analyzed with the VisionLab version 3.43 image analysis software to assess the quality of growth and to prevent subjective interpretation of the data. A 3- to 10-fold higher yield of discrete colonies was observed following automated inoculation with both the InoqulA and WASP systems than that with manual inoculation. The difference in performance between automated and manual inoculation was mainly observed at concentrations of >106 bacteria/ml. Inoculation with the InoqulA system allowed us to obtain significantly more discrete colonies than the WASP system at concentrations of >107 bacteria/ml. However, the level of difference observed was bacterial species dependent. Discrete colonies of bacteria present in 100- to 1,000-fold lower concentrations than the most concentrated populations in defined polymicrobial samples were not reproducibly recovered, even with the automated systems. The analysis of cloudy urine specimens showed that InoqulA inoculation provided a statistically significantly higher number of discrete colonies than that with WASP and manual inoculation. Consequently, the automated InoqulA inoculation greatly decreased the requirement for bacterial subculture and thus resulted in a significant reduction in the time to results, laboratory workload, and laboratory costs. PMID:25972424

  10. Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Additional information (Companion CD-ROM)

    International Nuclear Information System (INIS)

    2009-09-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO project and an evaluation of existing and future reactor designs the publication covers nuclear fuel cycle issues in detail. It is expected that this documentation will provide IAEA Member States and their nuclear engineers and designers, as well as policy makers with useful information on status and trends of future nuclear fuel cycle technologies. Due to the size of the full report it was decided to attach a CD-ROM in the back of the summary report

  11. The integrated manual and automatic control of complex flight systems

    Science.gov (United States)

    Schmidt, David K.

    1991-01-01

    Research dealt with the general area of optimal flight control synthesis for manned flight vehicles. The work was generic; no specific vehicle was the focus of study. However, the class of vehicles generally considered were those for which high authority, multivariable control systems might be considered, for the purpose of stabilization and the achievement of optimal handling characteristics. Within this scope, the topics of study included several optimal control synthesis techniques, control-theoretic modeling of the human operator in flight control tasks, and the development of possible handling qualities metrics and/or measures of merit. Basic contributions were made in all these topics, including human operator (pilot) models for multi-loop tasks, optimal output feedback flight control synthesis techniques; experimental validations of the methods developed, and fundamental modeling studies of the air-to-air tracking and flared landing tasks.

  12. Separations systems data base: a users' manual. Revision I

    International Nuclear Information System (INIS)

    Roddy, J.W.; McDowell, W.J.

    1981-01-01

    A separations systems data base (SEPSYS), designed specifically for the retrieval of information needed in chemical separations problems (i.e., how to perform a given separation under given conditions), is described. Included are descriptions of the basic methods of searching and retrieving information from the data base, the procedure for entering records into the data base, a listing of additional references concerning the computer information process, and an example of a typical record. The initial entries are concerned primarily with liquid-liquid extraction and liquid-solid ion exchange methods for metal ions and salts; however, the data base is constructed so that almost any separation process can be accommodated. Each record is indexed with information provided under the following fields: author; title; publication source; data of publication; organization sponsoring the work; brief abstract of the work; abstract number if the work has been so referenced, and/or abstractors initials; type of separation system used (e.g., flotation); specific or generic name of the separation agent used (e.g., acetylacetone); list of substances separated (e.g., gold, copper); qualitative description of the supporting medium or matrix containing the substances before separation (e.g., nitrate); type of literature where the record was printed (e.g., book); and type of information that the article contains. Each of these fields may be searched independently of the others (or in combination), and the last six fields contain specific key words that are listed in the report. Definitions are provided for the 36 information terms

  13. The OCaml system release 4.04: Documentation and user's manual

    OpenAIRE

    Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

    2016-01-01

    This manual documents the release 4.04 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  14. The OCaml system release 4.02: Documentation and user's manual

    OpenAIRE

    Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

    2014-01-01

    This manual documents the release 4.02 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  15. The OCaml system release 4.06: Documentation and user's manual

    OpenAIRE

    Leroy , Xavier; Doligez , Damien; Frisch , Alain; Garrigue , Jacques; Rémy , Didier; Vouillon , Jérôme

    2017-01-01

    This manual documents the release 4.06 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  16. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Downey, N.J.

    1994-12-14

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User`s Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered.

  17. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    International Nuclear Information System (INIS)

    Downey, N.J.

    1994-01-01

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User's Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered

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

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Jin, Young Ho

    1996-04-01

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

  19. System cost model user's manual, version 1.2

    International Nuclear Information System (INIS)

    Shropshire, D.

    1995-06-01

    The System Cost Model (SCM) was developed by Lockheed Martin Idaho Technologies in Idaho Falls, Idaho and MK-Environmental Services in San Francisco, California to support the Baseline Environmental Management Report sensitivity analysis for the U.S. Department of Energy (DOE). The SCM serves the needs of the entire DOE complex for treatment, storage, and disposal (TSD) of mixed low-level, low-level, and transuranic waste. The model can be used to evaluate total complex costs based on various configuration options or to evaluate site-specific options. The site-specific cost estimates are based on generic assumptions such as waste loads and densities, treatment processing schemes, existing facilities capacities and functions, storage and disposal requirements, schedules, and cost factors. The SCM allows customization of the data for detailed site-specific estimates. There are approximately forty TSD module designs that have been further customized to account for design differences for nonalpha, alpha, remote-handled, and transuranic wastes. The SCM generates cost profiles based on the model default parameters or customized user-defined input and also generates costs for transporting waste from generators to TSD sites

  20. Integrated dynamic landscape analysis and modeling system (IDLAMS) : installation manual.

    Energy Technology Data Exchange (ETDEWEB)

    Li, Z.; Majerus, K. A.; Sundell, R. C.; Sydelko, P. J.; Vogt, M. C.

    1999-02-24

    The Integrated Dynamic Landscape Analysis and Modeling System (IDLAMS) is a prototype, integrated land management technology developed through a joint effort between Argonne National Laboratory (ANL) and the US Army Corps of Engineers Construction Engineering Research Laboratories (USACERL). Dr. Ronald C. Sundell, Ms. Pamela J. Sydelko, and Ms. Kimberly A. Majerus were the principal investigators (PIs) for this project. Dr. Zhian Li was the primary software developer. Dr. Jeffrey M. Keisler, Mr. Christopher M. Klaus, and Mr. Michael C. Vogt developed the decision analysis component of this project. It was developed with funding support from the Strategic Environmental Research and Development Program (SERDP), a land/environmental stewardship research program with participation from the US Department of Defense (DoD), the US Department of Energy (DOE), and the US Environmental Protection Agency (EPA). IDLAMS predicts land conditions (e.g., vegetation, wildlife habitats, and erosion status) by simulating changes in military land ecosystems for given training intensities and land management practices. It can be used by military land managers to help predict the future ecological condition for a given land use based on land management scenarios of various levels of training intensity. It also can be used as a tool to help land managers compare different land management practices and further determine a set of land management activities and prescriptions that best suit the needs of a specific military installation.

  1. Design and control of electromagnetic clutch actuation system for automated manual transmission

    Science.gov (United States)

    Ranjan, Ashish; Prasanth, S.; Cherian, Fenin; Baskar, P.

    2017-11-01

    There is a growing interest towards Automatic Transmission in India as it provides better comfort and drivability. But the high cost of this system is limiting itself to be successful in the Indian markets. Due to this, Automated Manual Transmission (AMT) is considered which provides a better solution towards automation as it enhances the drivability and fuel consumption characteristics of a manual transmission at lower costs. However, torque lag and comfort are major issues with AMT which can be addressed by reducing the shift time. In this paper we describe an Electromagnetic Linear Clutch Actuator as a replacement to current electrohydraulic and electromechanical actuator. A control system for the actuator is presented and a clutch engagement strategy is also implemented which reduces the engagement time to 0.78 seconds while reducing jerk and torque lag. The actuator and control system is simulated on a MATLAB Simulink and agreeable results have been obtained.

  2. User’s manual to update the National Wildlife Refuge System Water Quality Information System (WQIS)

    Science.gov (United States)

    Chojnacki, Kimberly A.; Vishy, Chad J.; Hinck, Jo Ellen; Finger, Susan E.; Higgins, Michael J.; Kilbride, Kevin

    2013-01-01

    National Wildlife Refuges may have impaired water quality resulting from historic and current land uses, upstream sources, and aerial pollutant deposition. National Wildlife Refuge staff have limited time available to identify and evaluate potential water quality issues. As a result, water quality–related issues may not be resolved until a problem has already arisen. The National Wildlife Refuge System Water Quality Information System (WQIS) is a relational database developed for use by U.S. Fish and Wildlife Service staff to identify existing water quality issues on refuges in the United States. The WQIS database relies on a geospatial overlay analysis of data layers for ownership, streams and water quality. The WQIS provides summary statistics of 303(d) impaired waters and total maximum daily loads for the National Wildlife Refuge System at the national, regional, and refuge level. The WQIS allows U.S. Fish and Wildlife Service staff to be proactive in addressing water quality issues by identifying and understanding the current extent and nature of 303(d) impaired waters and subsequent total maximum daily loads. Water quality data are updated bi-annually, making it necessary to refresh the WQIS to maintain up-to-date information. This manual outlines the steps necessary to update the data and reports in the WQIS.

  3. User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

    Energy Technology Data Exchange (ETDEWEB)

    BRAYTON, D.D.

    2000-02-17

    User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572.

  4. User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

    International Nuclear Information System (INIS)

    BRAYTON, D.D.

    2000-01-01

    User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572

  5. Effectiveness of an automatic manual wheelchair braking system in the prevention of falls.

    Science.gov (United States)

    Martorello, Laura; Swanson, Edward

    2006-01-01

    The purpose of this study was to evaluate the effectiveness of an automatic manual wheelchair braking system in the reduction of falls for patients at high risk of falls while transferring to and from a manual wheelchair. The study design was a normative survey carried out through the use of a written questionnaire sent to 60 skilled nursing facilities to collect data from the medical charts, which identified patients at high risk for falls who used an automatic wheelchair braking system. The facilities participating in the study identified a frequency of falls of high-risk patients while transferring to and from the wheelchair ranging from 2 to 10 per year, with a median fall rate per facility of 4 falls. One year after the installation of the automatic wheelchair braking system, participating facilities demonstrated a reduction of zero to three falls during transfers by high-risk patients, with a median fall rate of zero falls. This represents a statistically significant reduction of 78% in the fall rate of high-risk patients while transferring to and from the wheelchair, t (18) = 6.39, p braking system for manual wheelchairs was installed. The application of the automatic braking system allows clients, families/caregivers, and facility personnel an increased safety factor for the reduction of falls from the wheelchair.

  6. A proposed power assisted system of manual wheelchair based on universal design for eldery

    Science.gov (United States)

    Susmartini, Susy; Pryadhitama, Ilham; Herdiman, Lobes; Wahyufitriani, Cindy

    2017-11-01

    Difficulties in walking is high percentage case in the limitations mobility of the elderly. An assisted technology commonly used to help the elderly who have walking difficulty is a manual wheelchair. However, the elderly frequently experiences difficulties in operating manual wheelchair due to gradually degradation of their physical condition. Preliminary study results showed that the average grip strength of the hands of seven elderly subjects was 13.8 ± 6.96 kg and the value is relatively weak. In addition, the mean maximum speed of 7 elderly subjects when doing to round the wheelchair is 0.6 ± 0.2m / s. This value is only 56.4% compared with an average speed of 20-23-year age group (8 males), which is 1.1 ± 0.1 m / s. This shows that the elderly who have walking difficulty have low grip strength and speed in operating a wheelchair. On the other hand, manual wheelchairs suffer an inadequate technology solution to solve the problem. Therefore, an assistive technology is proposed to create mobility aid to accommodate the elderly needs. One approach used is Universal Design. This paper proposes a system of intervention in the manual wheelchair through the 7 principles of Universal Design approach. The preliminary principle has not been able to accommodate the needs of the elderly will become a reference in the proposed design of this study.

  7. Operation and maintenance manual for septic holding tank system for project W-519, two double-wide construction support trailers

    International Nuclear Information System (INIS)

    MORTIMER, C.S.

    1999-01-01

    This manual was prepared to provide detailed information for the operation and maintenance of the sanitary wastewater holding system. It sets forth system operation and maintenance as well as failure response procedures

  8. GRACE manual

    International Nuclear Information System (INIS)

    Ishikawa, T.; Kawabata, S.; Shimizu, Y.; Kaneko, T.; Kato, K.; Tanaka, H.

    1993-02-01

    This manual is composed of three kinds of objects, theoretical background for calculating the cross section of elementary process, usage and technical details of the GRACE system. Throughout this manual we take the tree level process e + e - → W + W - γ as an example, including the e ± -scalar boson interactions. The real FORTRAN source code for this process is attached in the relevant sections as well as the results of calculation, which might be a great help for understanding the practical use of the system. (J.P.N.)

  9. The development of nuclear material accountability system - software user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

    1999-07-01

    We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig.

  10. Renewable Electric Plant Information System user interface manual: Paradox 7 Runtime for Windows

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The Renewable Electric Plant Information System (REPiS) is a comprehensive database with detailed information on grid-connected renewable electric plants in the US. The current version, REPiS3 beta, was developed in Paradox for Windows. The user interface (UI) was developed to facilitate easy access to information in the database, without the need to have, or know how to use, Paradox for Windows. The UI is designed to provide quick responses to commonly requested sorts of the database. A quick perusal of this manual will familiarize one with the functions of the UI and will make use of the system easier. There are six parts to this manual: (1) Quick Start: Instructions for Users Familiar with Database Applications; (2) Getting Started: The Installation Process; (3) Choosing the Appropriate Report; (4) Using the User Interface; (5) Troubleshooting; (6) Appendices A and B.

  11. Emission of Biophotons and Adjustable Sounds by the Fascial System: Review and Reflections for Manual Therapy.

    Science.gov (United States)

    Bordoni, Bruno; Marelli, Fabiola; Morabito, Bruno; Sacconi, Beatrice

    2018-01-01

    Every body structure is wrapped in connective tissue or fascia, creating a structural continuity that gives form and function to every tissue and organ. The fascial tissue is uniformly distributed throughout the body, enveloping, interacting with and permeating blood vessels, nerves, viscera, meninges, bones and muscles, creating various layers at different depths and forming a tridimensional metabolic and mechanical matrix. This article reviews the literature on the emission of biophotons and adjustable sounds by the fascial system, because these biological changes could be a means of local and systemic cellular communication and become another assessment tool for manual (therapy) practitioners. This is the first article that discusses these topics in a single text, attempting to bring such information into an area of application that is beneficial to osteopaths, chiropractors, and manual therapists.

  12. User's manual of self learning gas puffing system for plasma density control

    International Nuclear Information System (INIS)

    Tanahashi, S.

    1989-04-01

    Pre-programmed gas puffing is often used to get adequet plasma density wave forms in the pulse operating devices for fusion experiments. This method has a defect that preset values have to be adjusted manually in accordance with changes of out gassing rate in successive shots. In order to remove this defect, a self learning system has been developed so as to keep the plasma density close to a given reference waveform. After a few succesive shots, it accomplishes self learning and is ready to keep up with a gradual change of the wall condition. This manual gives the usage of the system and the program list written in BASIC and ASSEMBLER languages. (author)

  13. Image-guided system versus manual marking for toric intraocular lens alignment in cataract surgery.

    Science.gov (United States)

    Webers, Valentijn S C; Bauer, Noel J C; Visser, Nienke; Berendschot, Tos T J M; van den Biggelaar, Frank J H M; Nuijts, Rudy M M A

    2017-06-01

    To compare the accuracy of toric intraocular lens (IOL) alignment using the Verion Image-Guided System versus a conventional manual ink-marking procedure. University Eye Clinic Maastricht, Maastricht, the Netherlands. Prospective randomized clinical trial. Eyes with regular corneal astigmatism of at least 1.25 diopters (D) that required cataract surgery and toric IOL implantation (Acrysof SN6AT3-T9) were randomly assigned to the image-guided group or the manual-marking group. The primary outcome was the alignment of the toric IOL based on preoperative images and images taken immediately after surgery. Secondary outcome measures were residual astigmatism, uncorrected distance visual acuity (UDVA), and complications. The study enrolled 36 eyes (24 patients). The mean toric IOL misalignment was significantly less in the image-guided group than in the manual group 1 hour (1.3 degrees ± 1.6 [SD] versus 2.8 ± 1.8 degrees; P = .02) and 3 months (1.7 ± 1.5 degrees versus 3.1 ± 2.1 degrees; P image-guided group and manual group, respectively (P > .05). The mean UDVA was 0.03 ± 0.10 logarithm of minimum angle of resolution (logMAR) and 0.04 ± 0.09 logMAR, respectively (both P > .05). No intraoperative complications occurred during any surgery. The IOL misalignment was significantly less with digital marking than with manual marking; this did not result in a better UDVA or lower residual refractive astigmatism. Copyright © 2017 ASCRS and ESCRS. Published by Elsevier Inc. All rights reserved.

  14. Transportation Routing Analysis Geographic Information System (TRAGIS) User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, PE

    2003-09-18

    The Transportation Routing Analysis Geographic Information System (TRAGIS) model is used to calculate highway, rail, or waterway routes within the United States. TRAGIS is a client-server application with the user interface and map data files residing on the user's personal computer and the routing engine and network data files on a network server. The user's manual provides documentation on installation and the use of the many features of the model.

  15. The manual of a computer software 'FBR Plant Planning Design Prototype System'

    International Nuclear Information System (INIS)

    2003-10-01

    This is a manual of a computer software 'FBR Plant Planning Design Prototype System', which enables users to conduct case studies of deviated FBR design concepts based on 'MONJU'. The calculations simply proceed as the user clicks displayed buttons, therefore step-by-step explanation is supposed not be necessary. The following pages introduce only particular features of this software, i.e, each interactive screens, functions of buttons and consequences after clicks, and the quitting procedure. (author)

  16. Analysis of scenarios of the inclusion of fast reactors in the nuclear power of Russia in the context of sustainable development with the use of the INPRO methodology

    International Nuclear Information System (INIS)

    Usanov, V.I.; Kagramanyan, V.S.; Kalashnikov, A.G.; Korobeinikov, V.V.; Korobitsyn, V.E.; Moseyev, A.L.; Poplavskaya, E.V.

    2013-01-01

    Conclusions: • The two-component NES of VVER and BN reactors can meet some critical challenges of the present nuclear industry and provide a substantial contribution to enhancing sustainability of a national NP: – basically to solve up to 2050 the problem of the VVER SNF accumulation by using Pu from VVER in MOX fuel for BN reactors; – to ensure management of Pu from VVER to reduce it by 2070 to operational reserve and thus to enhance the NES proliferation resistance; – to save natural U and SWU and thus to facilitate U supply and enrichment capacities for planed deployment of VVERs in Russia and abroad. • Implementation of these opportunities might be a substance of the first phase of the NFC closure • While some INPRO indicators have shown remarkable advantages of the NES with BNs comparing to the present system, some issues in economics and NFC technologies have not got convincing answers. • These challenges along with a crucial safety issues are addressed in the Federal target programmes on transition to a CNFC with advanced FRs which are currently run in Russia

  17. The effect of bedding system selected by manual muscle testing on sleep-related cardiovascular functions.

    Science.gov (United States)

    Kuo, Terry B J; Li, Jia-Yi; Lai, Chun-Ting; Huang, Yu-Chun; Hsu, Ya-Chuan; Yang, Cheryl C H

    2013-01-01

    Different types of mattresses affect sleep quality and waking muscle power. Whether manual muscle testing (MMT) predicts the cardiovascular effects of the bedding system was explored using ten healthy young men. For each participant, two bedding systems, one inducing the strongest limb muscle force (strong bedding system) and the other inducing the weakest limb force (weak bedding system), were identified using MMT. Each bedding system, in total five mattresses and eight pillows of different firmness, was used for two continuous weeks at the participant's home in a random and double-blind sequence. A sleep log, a questionnaire, and a polysomnography were used to differentiate the two bedding systems. Heart rate variability and arterial pressure variability analyses showed that the strong bedding system resulted in decreased cardiovascular sympathetic modulation, increased cardiac vagal activity, and increased baroreceptor reflex sensitivity during sleep as compared to the weak bedding system. Different bedding systems have distinct cardiovascular effects during sleep that can be predicted by MMT.

  18. Concept of an immersive assistance system with augmented reality for the support of manual activities in radioactive production environments

    International Nuclear Information System (INIS)

    Eursch, Andreas A.

    2010-01-01

    The thesis on an immersive assistance system concept with augmented reality for the support of manual activities in radioactive production environments covers the following topics: analysis of the situation: production and use of radioactive materials, problem analysis of the work in the production facilities, necessity of manual activities, automation, prediction in hot cells; status of research and development; assistance system concept, immersive camera system; augmented reality support in hot cells; economic evaluation and generalization.

  19. National assessment study in Armenia using innovative nuclear reactors and fuel cycles methodology for an innovative nuclear systems in a country with small grid

    International Nuclear Information System (INIS)

    Sargsyan, V.H.; Galstyan, A.A.; Gevorgyan, A.A.

    2010-01-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in November 2000 under the aegis of the IAEA. Phases 1A and IB (first Part) of the Project were dedicated to elaboration, testing and validation of the INPRO Methodology. At the Technical Meeting in Vienna (13-15 October 2004) Armenia has proposed an assessment using the INPRO Methodology for an Innovative Nuclear Energy System in a country with a small electrical grid. Such kind of study helps Armenia in analysis of Innovative Nuclear Energy System (INS), including fuel cycle options, as well as shows applicability of INPRO methodology for small countries, like Armenia. This study was based on the results given in [3] and [4], and also on the main objectives, declared by the Government of Armenia in the paper 'Energy Sector Development Strategies in the Context of Economic Development in Armenia'

  20. Reference Manual for the System Advisor Model's Wind Power Performance Model

    Energy Technology Data Exchange (ETDEWEB)

    Freeman, J.; Jorgenson, J.; Gilman, P.; Ferguson, T.

    2014-08-01

    This manual describes the National Renewable Energy Laboratory's System Advisor Model (SAM) wind power performance model. The model calculates the hourly electrical output of a single wind turbine or of a wind farm. The wind power performance model requires information about the wind resource, wind turbine specifications, wind farm layout (if applicable), and costs. In SAM, the performance model can be coupled to one of the financial models to calculate economic metrics for residential, commercial, or utility-scale wind projects. This manual describes the algorithms used by the wind power performance model, which is available in the SAM user interface and as part of the SAM Simulation Core (SSC) library, and is intended to supplement the user documentation that comes with the software.

  1. Quantitative X ray analysis system. User's manual and guide to X ray fluorescence technique

    International Nuclear Information System (INIS)

    2009-01-01

    This guide covers trimmed and re-arranged version 3.6 of the Quantitative X ray Analysis System (QXAS) software package that includes the most frequently used methods of quantitative analysis. QXAS is a comprehensive quantitative analysis package that has been developed by the IAEA through research and technical contracts. Additional development has also been carried out in the IAEA Laboratories in Seibersdorf where QXAS was extensively tested. New in this version of the manual are the descriptions of the Voigt-profile peak fitting, the backscatter fundamental parameters' and emission-transmission methods of chemical composition analysis, an expanded chapter on the X ray fluorescence physics, and completely revised and increased number of practical examples of utilization of the QXAS software package. The analytical data accompanying this manual were collected in the IAEA Seibersdorf Laboratories in the years 2006/2007

  2. Long-term monitoring of soil gas fluxes with closed chambers using automated and manual systems

    Energy Technology Data Exchange (ETDEWEB)

    Scott, A.; Crichton, I.; Ball, B.C.

    1999-10-01

    The authors describe two gas sample collection techniques, each of which is used in conjunction with custom made automated or manually operated closed chambers. The automated system allows automatic collection of gas samples for simultaneous analysis of multiple trace gas efflux from soils, permitting long-term monitoring. Since the manual system is cheaper to produce, it can be replicated more than the automated and used to estimate spatial variability of soil fluxes. The automated chamber covers a soil area of 0.5 m{sup 2} and has a motor driven lid that remains operational throughout a range of weather conditions. Both systems use gas-tight containers of robust metal construction, which give good sample retention, thereby allowing long-term storage and convenience of transport from remote locations. The containers in the automated system are filled by pumping gas from the closed chamber via a multiway rotary valve. Stored samples from both systems are analyzed simultaneously for N{sub 2}O and CO{sub 2} using automated injection into laboratory-based gas chromatographs. The use of both collection systems is illustrated by results from a field experiment on sewage sludge disposal to land where N{sub 2}O fluxes were high. The automated gas sampling system permitted quantification of the marked temporal variability of concurrent N{sub 2}O and CO{sub 2} fluxes and allowed improved estimation of cumulative fluxes. The automated measurement approach yielded higher estimates of cumulative flux because integration of manual point-in-time observations missed a number of transient high-flux events.

  3. Integration of a browser based operator manual in the system environment of a process computer system; Integration eines browserbasierten Betriebshandbuchs in die Systemumgebung einer Prozessrechneranlage

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Andreas [Westinghouse Electric Germany GmbH (Germany); Erfle, Robert [DOSCO GmbH, Heidelberg (Germany); Feinkohl, Dirk [E.ON Kernkraft GmbH (Germany). Kernkraftwerk Unterweser

    2012-11-01

    The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

  4. A user's manual for the database management system of impact property

    International Nuclear Information System (INIS)

    Ryu, Woo Seok; Park, S. J.; Kong, W. S.; Jun, I.

    2003-06-01

    This manual is written for the management and maintenance of the impact database system for managing the impact property test data. The data base constructed the data produced from impact property test can increase the application of test results. Also, we can get easily the basic data from database when we prepare the new experiment and can produce better result by compare the previous data. To develop the database we must analyze and design carefully application and after that, we can offer the best quality to customers various requirements. The impact database system was developed by internet method using jsp(Java Server pages) tool

  5. FURNACE; a toroidal geometry neutronic program system method description and users manual

    International Nuclear Information System (INIS)

    Verschuur, K.A.

    1984-12-01

    The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor-design purposes, at acceptable calculational costs. A short description is given of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER is presented

  6. Users manual for an expert system (HSPEXP) for calibration of the hydrological simulation program; Fortran

    Science.gov (United States)

    Lumb, A.M.; McCammon, R.B.; Kittle, J.L.

    1994-01-01

    Expert system software was developed to assist less experienced modelers with calibration of a watershed model and to facilitate the interaction between the modeler and the modeling process not provided by mathematical optimization. A prototype was developed with artificial intelligence software tools, a knowledge engineer, and two domain experts. The manual procedures used by the domain experts were identified and the prototype was then coded by the knowledge engineer. The expert system consists of a set of hierarchical rules designed to guide the calibration of the model through a systematic evaluation of model parameters. When the prototype was completed and tested, it was rewritten for portability and operational use and was named HSPEXP. The watershed model Hydrological Simulation Program--Fortran (HSPF) is used in the expert system. This report is the users manual for HSPEXP and contains a discussion of the concepts and detailed steps and examples for using the software. The system has been tested on watersheds in the States of Washington and Maryland, and the system correctly identified the model parameters to be adjusted and the adjustments led to improved calibration.

  7. Comparison of Battery-Powered and Manual Bone Biopsy Systems for Core Needle Biopsy of Sclerotic Bone Lesions.

    Science.gov (United States)

    Cohen, Micah G; McMahon, Colm J; Kung, Justin W; Wu, Jim S

    2016-05-01

    The purpose of this study was to compare manual and battery-powered bone biopsy systems for diagnostic yield and procedural factors during core needle biopsy of sclerotic bone lesions. A total of 155 consecutive CT-guided core needle biopsies of sclerotic bone lesions were performed at one institution from January 2006 to November 2014. Before March 2012, lesions were biopsied with manual bone drill systems. After March 2012, most biopsies were performed with a battery-powered system and either noncoaxial or coaxial biopsy needles. Diagnostic yield, crush artifact, CT procedure time, procedure radiation dose, conscious sedation dose, and complications were compared between the manual and battery-powered core needle biopsy systems by Fisher exact test and t test. One-way ANOVA was used for subgroup analysis of the two battery-powered systems for procedure time and radiation dose. The diagnostic yield for all sclerotic lesions was 60.0% (93/155) and was significantly higher with the battery-powered system (73.0% [27/37]) than with the manual systems (55.9% [66/118]) (p = 0.047). There was no significant difference between the two systems in terms of crush artifact, procedure time, radiation dose, conscious sedation administered, or complications. In subgroup analysis, the coaxial battery-powered biopsies had shorter procedure times (p = 0.01) and lower radiation doses (p = 0.002) than the coaxial manual systems, but the noncoaxial battery-powered biopsies had longer average procedure times and higher radiation doses than the coaxial manual systems. In biopsy of sclerotic bone lesions, use of a battery-powered bone drill system improves diagnostic yield over use of a manual system.

  8. WSPEEDI-II system user's manual for a nuclear or radiological emergency

    International Nuclear Information System (INIS)

    Nakanishi, Chika; Sato, Sohei; Muto, Shigeo; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu

    2011-03-01

    Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, 'Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)' developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems. (author)

  9. PRIS-STATISTICS: Power Reactor Information System Statistical Reports. User's Manual

    International Nuclear Information System (INIS)

    2013-01-01

    The IAEA developed the Power Reactor Information System (PRIS)-Statistics application to assist PRIS end users with generating statistical reports from PRIS data. Statistical reports provide an overview of the status, specification and performance results of every nuclear power reactor in the world. This user's manual was prepared to facilitate the use of the PRIS-Statistics application and to provide guidelines and detailed information for each report in the application. Statistical reports support analyses of nuclear power development and strategies, and the evaluation of nuclear power plant performance. The PRIS database can be used for comprehensive trend analyses and benchmarking against best performers and industrial standards.

  10. Embedding librarianship in learning management systems a how-to-do-it manual for librarians

    CERN Document Server

    Tumbleson, Beth E

    2014-01-01

    Information literacy instruction is best when it is integrated into actual research, and in higher education that means embedding librarianship into the learning management system (LMS). This new How-To-Do-It Manual is geared towards academic librarians already working with classes in an LMS as well as those considering how to begin a pilot. Tumbleson and Burke, who surveyed 280 librarians for information on related activities, also use their own first-hand experience implementing an embedded librarianship program at their university to offer guidance and encouragement.

  11. The Montana Rivers Information System: Edit/entry program user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    The Montana Rivers Information System (MRIS) was initiated to assess the state`s fish, wildlife, and recreation value; and natural cultural and geologic features. The MRIS is now a set of data bases containing part of the information in the Natural Heritage Program natural features and threatened and endangered species data bases. The purpose of this User`s Manual is to: (1) describe to the user how to maintain the MRIS database of their choice by updating, changing, deleting, and adding records using the edit/entry programs; and (2) provide to the user all information and instructions necessary to complete data entry into the MRIS databases.

  12. GRESS [Gradient Enhanced Software System] Version 0.0 user's manual

    International Nuclear Information System (INIS)

    Horwedel, J.E.; Worley, B.A.; Oblow, E.M.; Pin, F.G.; Wright, R.Q.

    1988-10-01

    The primary objective of this manual is to provide a description of the Gradient Enhanced Software System (GRESS) and to explain how to use GRESS to enhance FORTRAN 77 models for gradient calculation. The use of the Extended Arithmetic Processor (EXAP) as the precompiler for GRESS is presented. A complete description of how to enhance a source code for forward propagation of derivatives using the calculus chain rule is provided. On option, EXAP can be used to generate derivatives and store them on a direct access device for subsequent solution of the numerical adjoint equations. Programming information is also provided to aid in the installation and maintenance of the software

  13. Operation and management manual of JT-60 experimental data analysis system

    International Nuclear Information System (INIS)

    Hirayama, Takashi; Morishima, Soichi

    2014-03-01

    In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is an operation and management manual the JT-60 experimental data analysis system. (author)

  14. Manually-Operated Crate Dismantlement System for Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Laffitte, John; Lagos, Leo; Morales, Miguel

    2002-01-01

    Los Alamos National Laboratory currently possesses between 500 and 800 fiberglass-reinforced plywood crates that contain hazardous materials that need to be decontaminated. To access the hazardous material, a system is needed to dismantle the crate. Currently, crates are dismantled by workers using hand-held tools. This technique has numerous disadvantages. One disadvantage is that it is difficult for a worker to hold the tool for an extended period of time in the awkward angles and positions necessary to fully size-reduce the crate. Other disadvantages of using hand tools include managing power cords and vacuum hoses, which become entangled or can act as tripping hazards. In order to improve the crate opening and size-reduction task, Florida International University's Hemispheric Center for Environmental Technology (HCET) is developing a manually operated crate dismantlement system. This versatile system is expected to greatly increase worker efficiency while decreasing fatigue and the possibility of accidents. (authors)

  15. Simulation model for wind energy storage systems. Volume II. Operation manual. [SIMWEST code

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume II, the SIMWEST operation manual, describes the usage of the SIMWEST program, the design of the library components, and a number of simple example simulations intended to familiarize the user with the program's operation. Volume II also contains a listing of each SIMWEST library subroutine.

  16. Manual of a suite of computer codes, EXPRESS (EXact PREparedness Supporting System)

    International Nuclear Information System (INIS)

    Chino, Masamichi

    1992-06-01

    The emergency response supporting system EXPRESS (EXact PREparedness Supporting System) is constructed in JAERI for low cost engineering work stations under the UNIX operation. The purpose of this system is real-time predictions of affected areas due to radioactivities discharged into atmosphere from nuclear facilities. The computational models in EXPRESS are the mass-consistent wind field model EXPRESS-I and the particle dispersion model EXPRESS-II for atmospheric dispersions. In order to attain the quick response even when the codes are used in a small-scale computer, a high-speed iteration method MILUCR (Modified Incomplete Linear Unitary Conjugate Residual) is applied to EXPRESS-I and kernel density method is to EXPRESS-II. This manual describes the model configurations, code structures, related files, namelists and sample outputs of EXPRESS-I and -II. (author)

  17. Program user's manual: cryogen system for the analysis for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    1979-04-01

    The Mirror Fusion Test Facility being designed and constructed at the Lawrence Livermore Laboratory requires a liquid helium liquefaction, storage, distribution, and recovery system and a liquid nitrogen storage and distribution system. To provide a powerful analytical tool to aid in the design evolution of this system through hardware, a thermodynamic fluid flow model was developed. This model allows the Lawrence Livermore Laboratory to verify that the design meets desired goals and to play what if games during the design evolution. For example, what if the helium flow rate is changed in the magnet liquid helium flow loop; how does this affect the temperature, fluid quality, and pressure. This manual provides all the information required to run all or portions of this program as desired. In addition, the program is constructed in a modular fashion so changes or modifications can be made easily to keep up with the evolving design

  18. Effectiveness of experimental system in children’s mastering of main manual motor skills

    Directory of Open Access Journals (Sweden)

    L. L. Galamandjuk

    2015-07-01

    Full Text Available Purpose: determine effectiveness of simulated system of pre-school age children motor functioning’s preventive development for mastering of main movements for manual skills. Material: in the research five years’ children (control group n=150 and experimental group n=120 participated. Results: it was determined that transition from uncomfortable to comfortable for a child conditions of exercises’ fulfillment facilitates quicker formation of required motor program. It is connected with the fact that, independent on orientation of manual motor asymmetry progressing of semi-spheres’ interaction takes place. This interaction is an important condition of increasing of child functioning’s effectiveness in different aspects. Achievement of such result was also facilitated by physical exercises, which children practiced at home. Functioning of physical culture instructor and kindergarten teachers was also important: they formed parents’ conscious position concerning importance of such trainings; recommended effective means and methods. Conclusions: application of the offered system ensures much better result than traditional approach to this problem. It is one of keys to prevention of negative tendencies in development of pre-school age children.

  19. Managing bottlenecks in manual automobile assembly systems using discrete event simulation

    Directory of Open Access Journals (Sweden)

    Dewa, M.

    2013-08-01

    Full Text Available Batch model lines are quite handy when the demand for each product is moderate. However, they are characterised by high work-in-progress inventories, lost production time when changing over models, and reduced flexibility when it comes to altering production rates as product demand changes. On the other hand, mixed model lines can offer reduced work-in-progress inventory and increased flexibility. The object of this paper is to illustrate that a manual automobile assembling system can be optimised through managing bottlenecks by ensuring high workstation utilisation, reducing queue lengths before stations and reducing station downtime. A case study from the automobile industry is used for data collection. A model is developed through the use of simulation software. The model is then verified and validated before a detailed bottleneck analysis is conducted. An operational strategy is then proposed for optimal bottleneck management. Although the paper focuses on improving automobile assembly systems in batch mode, the methodology can also be applied in single model manual and automated production lines.

  20. Accuracy of manual entry of drug administration data into an anesthesia information management system.

    Science.gov (United States)

    Avidan, Alexander; Dotan, Koren; Weissman, Charles; Cohen, Matan J; Levin, Phillip D

    2014-11-01

    Data on drug administration are entered manually into anesthesia information management systems (AIMS). This study examined whether these data are accurate regarding drug name, dose administered, and time of administration, and whether the stage of anesthesia influences data accuracy. Real-time observational data on drug administration during elective operations were compared with computerized information on drug administration entered by anesthesiologists. A trained observer (K.D.) performed the observations. Data were collected during 57 operations which included 596 separate occasions of drug administration by 22 anesthesiologists. No AIMS records were found for 90 (15.1%) occasions of drug administration (omissions), while there were 11 (1.8%) AIMS records where drug administration was not observed. The AIMS and observer data matched for drug name on 495 of 596 (83.1%) occasions, for dose on 439 of 495 (92.5%) occasions, and for time on 476 of 495 (96.2%) occasions. Amongst the 90 omitted records, 34 (37.8%) were for vasoactive drugs with 24 (27.7%) for small doses of hypnotics. Omissions occurred mostly during maintenance: 50 of 153 (24.6%), followed by induction: 30 of 325 (9.2%) and emergence: 10 of 57 (17.5%) (P < 0.001). Time and dose inaccuracies occurred mainly during induction, followed by maintenance and emergence; time inaccuracies were 7/325 (8.3%), 10/203 (4.9%), and 0/57 (0%), respectively (P = 0.07), and dose inaccuracies were 15/325 (4.6%), 3/203 (1.5%), and 1/57 (1.7%), respectively (P = 0.11). The range of accuracy varies when anesthesiologists manually enter drug administration data into an AIMS. Charting omissions represent the largest cause of inaccuracy, principally by omissions of records for vasopressors and small doses of hypnotic drugs. Manually entered drug administration data are not without errors. Accuracy of entering drug administration data remains the responsibility of the anesthesiologist.

  1. Manual Ability Classification System (MACS: reliability between therapists and parents in Brazil

    Directory of Open Access Journals (Sweden)

    Daniela B. R. Silva

    2015-02-01

    Full Text Available BACKGROUND: The Manual Ability Classification System (MACS has been widely used to describe the manual ability of children with cerebral palsy (CP; however its reliability has not been verified in Brazil. OBJECTIVE: To establish the inter- and intra-rater reliability of the Portuguese-Brazil version of the MACS by comparing the classifications given by therapists and parents of children with CP. METHOD: Data were obtained from 90 children with CP between the ages of 4 and 18 years, who were treated at the neurology and rehabilitation clinics of a Brazilian hospital. Therapists (an occupational therapist and a student classified manual ability (MACS through direct observation and information provided by parents. Therapists and parents used the Portuguese-Brazil version of the MACS. Intra- and inter-rater reliability was obtained using unweighted Kappa coefficient (k and intra-class correlation coefficient (ICC. The Chi-square test was used to identify the predominance of disagreements in the classification of parents and therapists. RESULTS: An almost perfect agreement resulted among therapists [K=0.90 (95% CI 0.83-0.97; ICC=0.97 (95%CI 0.96-0.98], as well as with intra-rater (therapists, with Kappa ranging between 0.83 and 0.95 and ICC between 0.96 and 0.99 for the evaluator with more and less experience in rehabilitation, respectively. The agreement between therapists and parents was fair [K=0.36 (95% CI 0.22-0.50; ICC=0.79 (95% CI 0.70-0.86]. CONCLUSIONS: The Portuguese version of the MACS is a reliable instrument to be used jointly by parents and therapists.

  2. Comparison of manual versus semiautomatic milk recording systems in dairy goats.

    Science.gov (United States)

    Ait-Saidi, A; Caja, G; Carné, S; Salama, A A K; Ghirardi, J J

    2008-04-01

    A total of 24 Murciano-Granadina dairy goats in early-midlactation were used to compare the labor time and data collection efficiency of using manual (M) vs. semiautomated (SA) systems for milk recording. Goats were milked once daily in a 2 x 12 parallel platform, with 6 milking units on each side. The M system used visual identification (ID) by large plastic ear tags, on-paper data recording, and data manually uploaded to a computer. The SA system used electronic ID, automatic ID, manual data recording on reader keyboard, and automatic data uploading to computer by Bluetooth connection. Data were collected for groups of 2 x 12 goats for 15 test days of each system during a period of 70 d. Time data were converted to a decimal scale. No difference in milk recording time between M and SA (1.32 +/- 0.03 and 1.34 +/- 0.03 min/goat, respectively) was observed. Time needed for transferring data to the computer was greater for M when compared with SA (0.20 +/- 0.01 and 0.05 +/- 0.01 min/goat). Overall milk recording time was greater in M than in SA (1.52 +/- 0.04 vs. 1.39 +/- 0.04 min/goat), the latter decreasing with operator training. Time for transferring milk recording data to the computer was 4.81 +/- 0.34 and 1.09 +/- 0.10 min for M and SA groups of 24 goats, respectively, but only increased by 0.19 min in SA for each additional 24 goats. No difference in errors of data acquisition was detected between M and SA systems during milk recording (0.6%), but an additional 1.1% error was found in the M system during data uploading. Predicted differences between M and SA increased with the number of goats processed on the test-day. Reduction in labor time cost ranged from euro0.5 to 12.9 (US$0.7 to 17.4) per milk recording, according to number of goats from 24 to 480 goats and accounted for 40% of the electronic ID costs. In conclusion, electronic ID was more efficient for labor costs and resulted in fewer data errors, the benefit being greater with trained operators and

  3. Manual on SFR R and D and Technology Monitoring System Based on Enterprise Project Management Solution

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

    2008-04-15

    This report is a manual on enterprise project management solution for R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. The prime goal of this system is to provide project manager with reliable and accurate information of status of progress, performance and resource allocation, and attain traceability and visibility of project implementation for effective project management. This report is composed of the three part. The first part is an introduction on microsoft project professional software that was used to monitor the progress, evaluate the results and analyze the resource distribution of the activities. The second makes a description of project plan and control, and the third part describes on collaboration and teamwork.

  4. STICAP: A linear circuit analysis program with stiff systems capability. Volume 1: Theory manual. [network analysis

    Science.gov (United States)

    Cooke, C. H.

    1975-01-01

    STICAP (Stiff Circuit Analysis Program) is a FORTRAN 4 computer program written for the CDC-6400-6600 computer series and SCOPE 3.0 operating system. It provides the circuit analyst a tool for automatically computing the transient responses and frequency responses of large linear time invariant networks, both stiff and nonstiff (algorithms and numerical integration techniques are described). The circuit description and user's program input language is engineer-oriented, making simple the task of using the program. Engineering theories underlying STICAP are examined. A user's manual is included which explains user interaction with the program and gives results of typical circuit design applications. Also, the program structure from a systems programmer's viewpoint is depicted and flow charts and other software documentation are given.

  5. Manual on SFR R and D and Technology Monitoring System Based on Enterprise Project Management Solution

    International Nuclear Information System (INIS)

    Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

    2008-04-01

    This report is a manual on enterprise project management solution for R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. The prime goal of this system is to provide project manager with reliable and accurate information of status of progress, performance and resource allocation, and attain traceability and visibility of project implementation for effective project management. This report is composed of the three part. The first part is an introduction on microsoft project professional software that was used to monitor the progress, evaluate the results and analyze the resource distribution of the activities. The second makes a description of project plan and control, and the third part describes on collaboration and teamwork

  6. Montana Rivers Information System : Edit/Entry Program User's Manual.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration; Montana Department of Fish, Wildlife and Parks

    1992-07-01

    The Montana Rivers Information System (MRIS) was initiated to assess the state`s fish, wildlife, and recreation value; and natural cultural, and geologic features. The MRIS is now a set of data bases containing part of the information in the Natural Heritage Program natural features and threatened and endangered species data bases and comprises of the Montana Interagency Stream Fisheries Database; the MDFWP Recreation Database; and the MDFWP Wildlife Geographic Information System. The purpose of this User`s Manual is to describe to the user how to maintain the MRIS database of their choice by updating, changing, deleting, and adding records using the edit/entry programs; and to provide to the user all information and instructions necessary to complete data entry into the MRIS databases.

  7. Manual for prototyping integrated and ecological arable farming systems (I/EAFS) in interaction with pilot farms

    NARCIS (Netherlands)

    Vereijken, P.

    1999-01-01

    A manual for prototyping Integrated and Ecological Arable Farming Systems (I/EAFS) in interaction with pilot farms is presented. It concerns a comprehensive and consistent approach of 5 steps. Step 1 is establishing a hierarchy of objectives considering the shortcomings of current farming systems in

  8. Operation manual of microbeam system in Takasaki for biological application (MiST-BA)

    International Nuclear Information System (INIS)

    Sakashita, Tetsuya; Yokota, Yuichiro; Wada, Seiichi; Funayama, Tomoo; Kobayashi, Yasuhiko

    2004-03-01

    Microbeam System is a powerful tool for micro-radiosurgery studies and direct investigation of cell-to-cell communications such as 'bystander effects'. Microbeam system in Takasaki for biological application (MiST-BA) has been developed for several years and applied to some cases. There were fate mapping of the cellular blastoderm stage egg of the silkworm and bystander effects such as inhibition of cell proliferation, induction of micronuclei, and so on. The aim of this report (operation manual) is to provide a simple and easy usage of MiST-BA for current and new users. MiST-BA consists of three parts; (1) Offline microscope control system for cell-finding. (2) Online microscope control system for cell-targeting and irradiating, and (3) Beam shutter control system for cell irradiation with a precise number of heavy ions. The report presents the outline of MiST-BA, the operation protocol of each part, examples of a microbeam irradiation experiment using CHO-K1 cells, silkworm eggs, and Tobacco protoplast cells, and Trouble shooting. (author)

  9. The effect of control and display lag on unmanned air system internal pilot manual landing performance

    Science.gov (United States)

    Lloyd, Marshall Everett

    An important characteristic of UASs is lag because it can become a considerable challenge to successful human-in-the-loop control. As such, UASs are designed and configured to minimize system lag, though this can increase acquisition and operation costs considerably. In an effort to cut costs, an organization may choose to accept greater risk and deploy a UAS with high system lag. Before this risk can be responsibly accepted, it must be quantified. While many studies have examined system lag, very few have been able to quantify the risk that various levels of lag pose to an internally piloted, manually landed UAS. This study attempted to do so by evaluating pilot landing performance in a simulator with 0 ms, 240 ms, and 1000 ms of additional lag. Various measures were used, including a novel coding technique. Results indicated that 1000 ms of lag was unsafe by all measures. They also indicate that 240 ms of lag degrades performance, but participants were able to successfully land the simulated aircraft. This study showed the utility of using several measures to evaluate the effect of lag on landing performance and it helped demonstrate that while 1000 ms poses a high risk, 240 ms of lag may be a much more manageable risk. Future research suggested by this research includes: investigating lag between 240 ms and 1000 ms, introducing different weather phenomena, developing system lag training techniques for operators, and investigating the effect of aides such as predictive displays and autopilot-assisted recovery.

  10. User's manual for the ARMLID (Argonne metallic lithium/isotopic dilution) tritium assay system

    International Nuclear Information System (INIS)

    Porges, K.G.; Bretscher, M.M.; Bennett, E.F.; DiIorio, G.; Mattas, R.F.; Lewandowski, E.F.

    1992-08-01

    The Argonne Metallic Lithium - Isotopic Dilution (ARMLID) system described in this report, originally developed at ANL for other purposes, was recently redeployed to measure the tritium production rate (TPR) in a series of US/Japanese collaborative fusion blanket integral experiments, involving large assemblies of fusion breeder blanket materials that were irradiated with a fusion neutron source at FNS/JAERI, Japan. Whereas previous uses of the ARMUD scheme involved just a few samples, its application infusion blanket TPR mapping called for large sample numbers per experiment, implying a commensurate scale of sample fabrication and encapsulation, on one hand, and tritium extraction and counting on the other hand. To shorten the time required for these various tasks, yet still yield reliable and accurate results, both the sample fabrication - encapsulation facility and the tritium extraction system had to be extensively revised from original versions that were designed for accuracy, but not necessarily for speed. The present report describes overall revisions in sufficient detail to serve as a User's Manual for this facility, and/or suggest how a new system might be put together. Either possibility may develop in the near future, in support of ITER design studies. Preliminary and partial descriptions of various aspects and features of the system were presented orally, in the course of annual ANL/JAERI/UCLA ''workshops'', over the last 34 years, as well as elsewhere

  11. User's manual of SECOM2: a computer code for seismic system reliability analysis

    International Nuclear Information System (INIS)

    Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Tamura, Kazuo

    2002-03-01

    This report is the user's manual of seismic system reliability analysis code SECOM2 (Seismic Core Melt Frequency Evaluation Code Ver.2) developed at the Japan Atomic Energy Research Institute for systems reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as: Calculation of component failure probabilities based on the response factor method, Extraction of minimal cut sets (MCSs), Calculation of conditional system failure probabilities for given seismic motion levels at the site of an NPP, Calculation of accident sequence frequencies and the core damage frequency (CDF) with use of the seismic hazard curve, Importance analysis using various indicators, Uncertainty analysis, Calculation of the CDF taking into account the effect of the correlations of responses and capacities of components, and Efficient sensitivity analysis by changing parameters on responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about response and capacity of components and seismic hazard curve for the NPP site as inputs. This report presents the models and methods applied in the SECOM2 code and how to use those functions. (author)

  12. FMEA of manual and automated methods for commissioning a radiotherapy treatment planning system.

    Science.gov (United States)

    Wexler, Amy; Gu, Bruce; Goddu, Sreekrishna; Mutic, Maya; Yaddanapudi, Sridhar; Olsen, Lindsey; Harry, Taylor; Noel, Camille; Pawlicki, Todd; Mutic, Sasa; Cai, Bin

    2017-09-01

    To evaluate the level of risk involved in treatment planning system (TPS) commissioning using a manual test procedure, and to compare the associated process-based risk to that of an automated commissioning process (ACP) by performing an in-depth failure modes and effects analysis (FMEA). The authors collaborated to determine the potential failure modes of the TPS commissioning process using (a) approaches involving manual data measurement, modeling, and validation tests and (b) an automated process utilizing application programming interface (API) scripting, preloaded, and premodeled standard radiation beam data, digital heterogeneous phantom, and an automated commissioning test suite (ACTS). The severity (S), occurrence (O), and detectability (D) were scored for each failure mode and the risk priority numbers (RPN) were derived based on TG-100 scale. Failure modes were then analyzed and ranked based on RPN. The total number of failure modes, RPN scores and the top 10 failure modes with highest risk were described and cross-compared between the two approaches. RPN reduction analysis is also presented and used as another quantifiable metric to evaluate the proposed approach. The FMEA of a MTP resulted in 47 failure modes with an RPN ave of 161 and S ave of 6.7. The highest risk process of "Measurement Equipment Selection" resulted in an RPN max of 640. The FMEA of an ACP resulted in 36 failure modes with an RPN ave of 73 and S ave of 6.7. The highest risk process of "EPID Calibration" resulted in an RPN max of 576. An FMEA of treatment planning commissioning tests using automation and standardization via API scripting, preloaded, and pre-modeled standard beam data, and digital phantoms suggests that errors and risks may be reduced through the use of an ACP. © 2017 American Association of Physicists in Medicine.

  13. User's Manual for the New England Water-Use Data System (NEWUDS)

    Science.gov (United States)

    Horn, Marilee A.

    2003-01-01

    Water is used in a variety of ways that need to be understood for effective management of water resources. Water-use activities need to be categorized and included in a database management system to understand current water uses and to provide information to water-resource management policy decisionmakers. The New England Water-Use Data System (NEWUDS) is a complex database developed to store water-use information that allows water to be tracked from a point of water-use activity (called a 'Site'), such as withdrawal from a resource (reservoir or aquifer), to a second Site, such as distribution to a user (business or irrigator). NEWUDS conceptual model consists of 10 core entities: system, owner, address, location, site, data source, resource, conveyance, transaction/rate, and alias, with tables available to store user-defined details. Three components--site (with both a From Site and a To Site), a conveyance that connects them, and a transaction/rate associated with the movement of water over a specific time interval form the core of the basic NEWUDS network model. The most important step in correctly translating real-world water-use activities into a storable format in NEWUDS depends on choosing the appropriate sites and linking them correctly in a network to model the flow of water from the initial From Site to the final To Site. Ten water-use networks representing real-world activities are described--three withdrawal networks, three return networks, two user networks, two complex community-system networks. Ten case studies of water use, one for each network, also are included in this manual to illustrate how to compile, store, and retrieve the appropriate data. The sequence of data entry into tables is critical because there are many foreign keys. The recommended core entity sequence is (1) system, (2) owner, (3) address, (4) location, (5) site, (6) data source, (7) resource, (8) conveyance, (9) transaction, and (10) rate; with (11) alias and (12) user

  14. PQLX: A seismic data quality control system description, applications, and users manual

    Science.gov (United States)

    McNamara, Daniel E.; Boaz, Richard I.

    2011-01-01

    We present a detailed description and users manual for a new tool to evaluate seismic station performance and characteristics by providing quick and easy transitions between visualizations of the frequency and time domains. The software is based on the probability density functions (PDF) of power spectral densities (PSD) (McNamara and Buland, 2004) and builds on the original development of the PDF stand-alone software system (McNamara and Boaz, 2005) and the seismological data viewer application PQL (IRIS-PASSCAL Quick Look) and PQLII (available through the IRIS PASSCAL program: http://www.passcal.nmt.edu/content/pql-ii-program-viewing-data). With PQLX (PQL eXtended), computed PSDs are stored in a MySQL database, allowing a user to access specific time periods of PSDs (PDF subsets) and time series segments through a GUI-driven interface. The power of the method and software lies in the fact that there is no need to screen the data for system transients, earthquakes, or general data artifacts, because they map into a background probability level. In fact, examination of artifacts related to station operation and episodic cultural noise allow us to estimate both the overall station quality and a baseline level of Earth noise at each site. The output of this analysis tool is useful for both operational and scientific applications. Operationally, it is useful for characterizing the current and past performance of existing broadband stations, for conducting tests on potential new seismic station locations, for evaluating station baseline noise levels (McNamara and others, 2009), for detecting problems with the recording system or sensors, and for evaluating the overall quality of data and metadata. Scientifically, the tool allows for mining of PSDs for investigations on the evolution of seismic noise (for example, Aster and others, 2008; and Aster and others, 2010) and other phenomena. Currently, PQLX is operational at several organizations including the USGS National

  15. Computer-Aided System Engineering and Analysis (CASE/A) Programmer's Manual, Version 5.0

    Science.gov (United States)

    Knox, J. C.

    1996-01-01

    The Computer Aided System Engineering and Analysis (CASE/A) Version 5.0 Programmer's Manual provides the programmer and user with information regarding the internal structure of the CASE/A 5.0 software system. CASE/A 5.0 is a trade study tool that provides modeling/simulation capabilities for analyzing environmental control and life support systems and active thermal control systems. CASE/A has been successfully used in studies such as the evaluation of carbon dioxide removal in the space station. CASE/A modeling provides a graphical and command-driven interface for the user. This interface allows the user to construct a model by placing equipment components in a graphical layout of the system hardware, then connect the components via flow streams and define their operating parameters. Once the equipment is placed, the simulation time and other control parameters can be set to run the simulation based on the model constructed. After completion of the simulation, graphical plots or text files can be obtained for evaluation of the simulation results over time. Additionally, users have the capability to control the simulation and extract information at various times in the simulation (e.g., control equipment operating parameters over the simulation time or extract plot data) by using "User Operations (OPS) Code." This OPS code is written in FORTRAN with a canned set of utility subroutines for performing common tasks. CASE/A version 5.0 software runs under the VAX VMS(Trademark) environment. It utilizes the Tektronics 4014(Trademark) graphics display system and the VTIOO(Trademark) text manipulation/display system.

  16. Operators Manual and Technical Reference for the Z-Beamlet Phase Modulation Failsafe System: Version 1.

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, Darrell J.

    2014-09-01

    The need for pulse energies exceeding 4 kJ and pulse lengths [?] 2 ns in Sandia's Z-Beamlet laser (ZBL) requires that the single-frequency spectrum of its fiber-laser master oscillator be converted to a phase modulated spectrum with a modulation in dex [?] 5. Because accidental injection of single-frequency light into ZBL could result i n damage to optical materials from transverse stimulated Brillouin scattering, the presence of phase modulated (PM) light must be monitored by a reliable failsafe system that can stop a las er shot within of a few 10's of ns following a failure of the PM system. This requirement is met by combining optical heterodyne detection with high-speed electronics to indicate the pres ence or absence of phase modulated light. The transition time for the failsafe signal resultin g from a sudden failure using this technique is approximately 35 ns. This is sufficiently short to safely stop a single-frequency laser pulse from leaving ZBL's regenerative amplifier with a n approximately 35 ns margin of safety. This manual and technical reference contains detai led instructions for daily use of the PM failsafe system and provides enough additional informat ion for its maintenance and repair.

  17. Operations and Maintenance Manual for Full-Scale Bioventing System at FSA-1, Air Force Plant 4, Fort Worth, Texas

    National Research Council Canada - National Science Library

    1996-01-01

    This Operations and Maintenance (O&M) Manual has been created as a guide for monitoring and maintaining the performance of the full-scale bioventing blower system and vent well plumbing at FSA-1 at Air Force Plant 4 (AFP4), Texas...

  18. Design, analysis and modeling of a novel hybrid powertrain system based on hybridized automated manual transmission

    Science.gov (United States)

    Wu, Guang; Dong, Zuomin

    2017-09-01

    Hybrid electric vehicles are widely accepted as a promising short to mid-term technical solution due to noticeably improved efficiency and lower emissions at competitive costs. In recent years, various hybrid powertrain systems were proposed and implemented based on different types of conventional transmission. Power-split system, including Toyota Hybrid System and Ford Hybrid System, are well-known examples. However, their relatively low torque capacity, and the drive of alternative and more advanced designs encouraged other innovative hybrid system designs. In this work, a new type of hybrid powertrain system based hybridized automated manual transmission (HAMT) is proposed. By using the concept of torque gap filler (TGF), this new hybrid powertrain type has the potential to overcome issue of torque gap during gearshift. The HAMT design (patent pending) is described in details, from gear layout and design of gear ratios (EV mode and HEV mode) to torque paths at different gears. As an analytical tool, mutli-body model of vehicle equipped with this HAMT was built to analyze powertrain dynamics at various steady and transient modes. A gearshift was decomposed and analyzed based basic modes. Furthermore, a Simulink-SimDriveline hybrid vehicle model was built for the new transmission, driveline and vehicle modular. Control strategy has also been built to harmonically coordinate different powertrain components to realize TGF function. A vehicle launch simulation test has been completed under 30% of accelerator pedal position to reveal details during gearshift. Simulation results showed that this HAMT can eliminate most torque gap that has been persistent issue of traditional AMT, improving both drivability and performance. This work demonstrated a new type of transmission that features high torque capacity, high efficiency and improved drivability.

  19. NSDNA: a manually curated database of experimentally supported ncRNAs associated with nervous system diseases.

    Science.gov (United States)

    Wang, Jianjian; Cao, Yuze; Zhang, Huixue; Wang, Tianfeng; Tian, Qinghua; Lu, Xiaoyu; Lu, Xiaoyan; Kong, Xiaotong; Liu, Zhaojun; Wang, Ning; Zhang, Shuai; Ma, Heping; Ning, Shangwei; Wang, Lihua

    2017-01-04

    The Nervous System Disease NcRNAome Atlas (NSDNA) (http://www.bio-bigdata.net/nsdna/) is a manually curated database that provides comprehensive experimentally supported associations about nervous system diseases (NSDs) and noncoding RNAs (ncRNAs). NSDs represent a common group of disorders, some of which are characterized by high morbidity and disabilities. The pathogenesis of NSDs at the molecular level remains poorly understood. ncRNAs are a large family of functionally important RNA molecules. Increasing evidence shows that diverse ncRNAs play a critical role in various NSDs. Mining and summarizing NSD-ncRNA association data can help researchers discover useful information. Hence, we developed an NSDNA database that documents 24 713 associations between 142 NSDs and 8593 ncRNAs in 11 species, curated from more than 1300 articles. This database provides a user-friendly interface for browsing and searching and allows for data downloading flexibility. In addition, NSDNA offers a submission page for researchers to submit novel NSD-ncRNA associations. It represents an extremely useful and valuable resource for researchers who seek to understand the functions and molecular mechanisms of ncRNA involved in NSDs. © The Author(s) 2016. Published by Oxford University Press on behalf of Nucleic Acids Research.

  20. Selecting healthcare information systems provided by third-party vendors: a mind map beyond the manuals.

    Science.gov (United States)

    Gortzis, Lefteris G

    2010-01-01

    The selection of a new healthcare information system (HIS) has always been a daunting process for clinicians, health care providers and policy makers. The objective of this study is to present the lessons learned and the main findings from several relevant case studies to support this process. Data were collected by retrospectively reviewing the summative results of three well-established systems, acquiring feedback from two E.U. projects, and conducting semi-structured interviews with a number of collaborators involved in electronic healthcare interventions. Selection issues were identified and classified into the following five categories: (i) data creation, (ii) data management, (iii) data sharing, (iv) data presentation and (v) modules management. A mind map was also structured to provide a more manageable list of issues concerning the most common electronic clinical technologies (e-CT). The vendor manual is intended as an overview of the merchandise e-CT and therefore has limited potential in supporting effectively the selection process of a new HIS. The present classification and the mind map - based on lessons learned - provide a ready-to-use toolkit for supporting the HIS selection process when healthcare organisations are unable to employ research development groups to lay the groundwork for building a new HIS from scratch.

  1. Integrated Reliability and Risk Analysis System (IRRAS), Version 2.5: Reference manual

    International Nuclear Information System (INIS)

    Russell, K.D.; McKay, M.K.; Sattison, M.B.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

    1991-03-01

    The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the user the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification. Version 1.0 of the IRRAS program was released in February of 1987. Since that time, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 2.5 and is the subject of this Reference Manual. Version 2.5 of IRRAS provides the same capabilities as Version 1.0 and adds a relational data base facility for managing the data, improved functionality, and improved algorithm performance. 7 refs., 348 figs

  2. EMSL Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Foster, Nancy S.

    2009-06-18

    This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

  3. EMSL Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Foster, Nancy S.

    2009-03-25

    This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

  4. Operations and Maintenance Manual for Expanded Bioventing System Site FC-2 Kelly AFB, Texas

    National Research Council Canada - National Science Library

    1996-01-01

    This Operations and Maintenance Manual has been created as a guide for monitoring and maintaining the performance of the bioventing blower and vent well plumbing at the Fire Training Area (Site FC-2...

  5. The Intelligent Monitoring System: Generic Database Interface (GDI). User Manual. Revision

    Science.gov (United States)

    1994-01-03

    Summary of Lo=catos Nan* Decufptin Directory Location User Manual FrameMaker ’ source organized inlo, a book UBSW~ftbendb~doclim/user-manual named gdibk A...functions. LNSRCf1bgenrdb/srC I. Framemaker is a docment publishing tool fium Fame Technology Cororation Baseline: 21.1 3-1 anoAW ftnua ?bewd uw on 3.2

  6. Comparison of the cleaning capacity of Mtwo and ProTaper rotary systems and manual instruments in primary teeth

    Directory of Open Access Journals (Sweden)

    Mohammad Reza Azar

    2012-01-01

    Full Text Available Background: Root canal cleaning is an important step in endodontic therapy. In order to develop better techniques, a new generation of endodontic instruments has been designed. The aim of this study was to compare the effectiveness of manual K-files (Mani Co, Tokyo, Japan and two rotary systems-Mtwo (Dentsply-Maillefer, Ballaigues, Switzerland and ProTaper (VDW, Munich, Germany-for root canal preparation in primary molars. Materials and Methods: India ink was injected to 160 mesiobuccal and distal root canals of mandibular primary molars. The teeth were randomly divided into three experimental groups and one control group. In each experimental group, either manual instruments (K-files or rotary instruments (Mtwo or ProTaper were used to prepare root canals. After cleaning the canals and clearing the teeth, ink removal was evaluated with a stereomicroscope. Statistical analysis was done with Kruskal-Wallis and Friedman tests. Results: There were no significant differences in cleaning efficiency between manual and rotary instruments. Only ProTaper files performed significantly better in the coronal and middle thirds than in the apical third of the root canal. Conclusion: Manual K-files and the Mtwo and ProTaper rotary systems showed equally acceptable cleaning ability in primary molar root canals.

  7. Nuclear power plant control room crew task analysis database: SEEK system. Users manual

    International Nuclear Information System (INIS)

    Burgy, D.; Schroeder, L.

    1984-05-01

    The Crew Task Analysis SEEK Users Manual was prepared for the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission. It is designed for use with the existing computerized Control Room Crew Task Analysis Database. The SEEK system consists of a PR1ME computer with its associated peripherals and software augmented by General Physics Corporation SEEK database management software. The SEEK software programs provide the Crew Task Database user with rapid access to any number of records desired. The software uses English-like sentences to allow the user to construct logical sorts and outputs of the task data. Given the multiple-associative nature of the database, users can directly access the data at the plant, operating sequence, task or element level - or any combination of these levels. A complete description of the crew task data contained in the database is presented in NUREG/CR-3371, Task Analysis of Nuclear Power Plant Control Room Crews (Volumes 1 and 2)

  8. A manual for a Laboratory Information Management System (LIMS) for light stable isotopes

    Science.gov (United States)

    Coplen, Tyler B.

    1998-01-01

    The reliability and accuracy of isotopic data can be improved by utilizing database software to (i) store information about samples, (ii) store the results of mass spectrometric isotope-ratio analyses of samples, (iii) calculate analytical results using standardized algorithms stored in a database, (iv) normalize stable isotopic data to international scales using isotopic reference materials, and (v) generate multi-sheet paper templates for convenient sample loading of automated mass-spectrometer sample preparation manifolds. Such a database program is presented herein. Major benefits of this system include (i) an increase in laboratory efficiency, (ii) reduction in the use of paper, (iii) reduction in workload due to the elimination or reduction of retyping of data by laboratory personnel, and (iv) decreased errors in data reported to sample submitters. Such a database provides a complete record of when and how often laboratory reference materials have been analyzed and provides a record of what correction factors have been used through time. It provides an audit trail for stable isotope laboratories. Since the original publication of the manual for LIMS for Light Stable Isotopes, the isotopes 3 H, 3 He, and 14 C, and the chlorofluorocarbons (CFCs), CFC-11, CFC-12, and CFC-113, have been added to this program.

  9. Cleaning capacity promoted by motor-driven or manual instrumentation using ProTaper Universal system: Histological analysis

    OpenAIRE

    da Frota, Matheus Franco; Filho, Idomeo Bonetti; Berbert, F?bio Luiz Camargo Villela; Sponchiado, Emilio Carlos; Marques, Andr? Augusto Franco; Garcia, Lucas da Fonseca Roberti

    2013-01-01

    Aim: The aim of this study was to assess the cleaning capacity of the Protaper system using motor-driven or manual instrumentation. Materials and Methods: Ten mandibular molars were randomly separated into 2 groups (n = 5) according to the type of instrumentation performed, as follows: Group 1 - instrumentation with rotary nickel-titanium (Ni-Ti) files using ProTaper Universal System (Dentsply/Maillefer); and, Group 2 - instrumentation with Ni-Ti hand files using ProTaper Universal (Den...

  10. WASTES: Wastes system transportation and economic simulation: Version 2, Programmer's reference manual

    International Nuclear Information System (INIS)

    Buxbaum, M.E.; Shay, M.R.

    1986-11-01

    The WASTES Version II (WASTES II) Programmer's Reference Manual was written to document code development activities performed under the Monitored Retrievable Storage (MRS) Program at Pacific Northwest Laboratory (PNL). The manual will also serve as a valuable tool for programmers involved in maintenance of and updates to the WASTES II code. The intended audience for this manual are experienced FORTRAN programmers who have only a limited knowledge of nuclear reactor operation, the nuclear fuel cycle, or nuclear waste management practices. It is assumed that the readers of this manual have previously reviewed the WASTES II Users Guide published as PNL Report 5714. The WASTES II code is written in FORTRAN 77 as an extension to the SLAM commercial simulation package. The model is predominately a FORTRAN based model that makes extensive use of the SLAM file maintenance and time management routines. This manual documents the general manner in which the code is constructed and the interactions between SLAM and the WASTES subroutines. The functionality of each of the major WASTES subroutines is illustrated with ''block flow'' diagrams. The basic function of each of these subroutines, the algorithms used in them, and a discussion of items of particular note in the subroutine are reviewed in this manual. The items of note may include an assumption, a coding practice that particularly applies to a subroutine, or sections of the code that are particularly intricate or whose mastery may be difficult. The appendices to the manual provide extensive detail on the use of arrays, subroutines, included common blocks, parameters, variables, and files

  11. Comparison of the cleaning capacity of Mtwo and Pro Taper rotary systems and manual instruments in primary teeth

    Science.gov (United States)

    Azar, Mohammad Reza; Safi, Laya; Nikaein, Afshin

    2012-01-01

    Background: Root canal cleaning is an important step in endodontic therapy. In order to develop better techniques, a new generation of endodontic instruments has been designed. The aim of this study was to compare the effectiveness of manual K-files (Mani Co, Tokyo, Japan) and two rotary systems–Mtwo (Dentsply-Maillefer, Ballaigues, Switzerland) and ProTaper (VDW, Munich, Germany)–for root canal preparation in primary molars. Materials and Methods: India ink was injected to 160 mesiobuccal and distal root canals of mandibular primary molars. The teeth were randomly divided into three experimental groups and one control group. In each experimental group, either manual instruments (K-files) or rotary instruments (Mtwo or ProTaper) were used to prepare root canals. After cleaning the canals and clearing the teeth, ink removal was evaluated with a stereomicroscope. Statistical analysis was done with Kruskal–Wallis and Friedman tests. Results: There were no significant differences in cleaning efficiency between manual and rotary instruments. Only ProTaper files performed significantly better in the coronal and middle thirds than in the apical third of the root canal. Conclusion: Manual K-files and the Mtwo and ProTaper rotary systems showed equally acceptable cleaning ability in primary molar root canals. PMID:22623929

  12. Operating system for a real-time multiprocessor propulsion system simulator. User's manual

    Science.gov (United States)

    Cole, G. L.

    1985-01-01

    The NASA Lewis Research Center is developing and evaluating experimental hardware and software systems to help meet future needs for real-time, high-fidelity simulations of air-breathing propulsion systems. Specifically, the real-time multiprocessor simulator project focuses on the use of multiple microprocessors to achieve the required computing speed and accuracy at relatively low cost. Operating systems for such hardware configurations are generally not available. A real time multiprocessor operating system (RTMPOS) that supports a variety of multiprocessor configurations was developed at Lewis. With some modification, RTMPOS can also support various microprocessors. RTMPOS, by means of menus and prompts, provides the user with a versatile, user-friendly environment for interactively loading, running, and obtaining results from a multiprocessor-based simulator. The menu functions are described and an example simulation session is included to demonstrate the steps required to go from the simulation loading phase to the execution phase.

  13. Performance of automated and manual coding systems for occupational data: a case study of historical records.

    Science.gov (United States)

    Patel, Mehul D; Rose, Kathryn M; Owens, Cindy R; Bang, Heejung; Kaufman, Jay S

    2012-03-01

    Occupational data are a common source of workplace exposure and socioeconomic information in epidemiologic research. We compared the performance of two occupation coding methods, an automated software and a manual coder, using occupation and industry titles from U.S. historical records. We collected parental occupational data from 1920-40s birth certificates, Census records, and city directories on 3,135 deceased individuals in the Atherosclerosis Risk in Communities (ARIC) study. Unique occupation-industry narratives were assigned codes by a manual coder and the Standardized Occupation and Industry Coding software program. We calculated agreement between coding methods of classification into major Census occupational groups. Automated coding software assigned codes to 71% of occupations and 76% of industries. Of this subset coded by software, 73% of occupation codes and 69% of industry codes matched between automated and manual coding. For major occupational groups, agreement improved to 89% (kappa = 0.86). Automated occupational coding is a cost-efficient alternative to manual coding. However, some manual coding is required to code incomplete information. We found substantial variability between coders in the assignment of occupations although not as large for major groups.

  14. Manual of low-capacity bioenergy systems; Handbuch Bioenergie-Kleinanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, H. (ed.); Thuneke, K.; Hoeldrich, A.; Rossmann, P.; Meier, L.; Eismann, H.; Nielsen, H.

    2003-02-01

    The manual attempts a systematic presentation of the current knowledge on the use of biogenic fuels in low-capacity systems. Fundamental and complex technical knowledge is presented in a simple and popular manner, and technical, organisational, economic and legal problems relating to practical application are presented with a view to practical application. This makes the book interesting as a projecting and decision aid for private and public decision-makers. The book addresses private households, small industries, planners and architects, fuel producers and retailers, private and public consultants, and others. (orig.) [German] Im vorliegenden Leitfaden wird versucht, das Wissen ueber den Einsatz biogener Brennstoffe in kleineren Anlagen zu systematisieren und aufzubereiten. Dabei wird der Versuch unternommen, einerseits grundlegende, zum Teil komplexe Zusammenhaenge allgemein verstaendlich darzustellen und andererseits anwendungsbezogene technische, organisatorische, wirtschaftliche und rechtliche Fragen umfassend zu beantworten. Dadurch kann der Leitfaden als Projektierungs- und Ausfuehrungshilfe fuer die am Prozess der Brennstoffbereitstellung und -nutzung beteiligten Akteure aber auch fuer die beratenden oeffentlichen und privaten Einrichtungen dienen. Im Einzelnen soll der Leitfaden - Interesse an der Realisierung eigener Projektideen fuer die Biomassenutzung wecken, - die Beurteilung eigener Spielraeume fuer die Biomassenutzung erleichtern, - Basiswissen vermitteln, - einen Ueberblick ueber die technischen Moeglichkeiten im Bereich kleiner Anlagen geben, - Hilfestellung bei der Bewertung von biogenen Brennstoffen und ihren Einsatzmoeglichkeiten bieten, - die Systemauswahl und -konfiguration erleichtern, - Sicherheit im Umgang mit den Fachbegriffen vermitteln, - die rechtlichen Rahmenbedingungen vorstellen, - Planungsdaten liefern und Fehleinschaetzungen vermeiden helfen, - Verbesserungsmoeglichkeiten an bereits existierenden Anlagen aufzeigen, - die

  15. Comparison of the cleaning capacity of Mtwo and ProTaper rotary systems and manual instruments in primary teeth

    OpenAIRE

    Mohammad Reza Azar; Laya Safi; Afshin Nikaein

    2012-01-01

    Background: Root canal cleaning is an important step in endodontic therapy. In order to develop better techniques, a new generation of endodontic instruments has been designed. The aim of this study was to compare the effectiveness of manual K-files (Mani Co, Tokyo, Japan) and two rotary systems-Mtwo (Dentsply-Maillefer, Ballaigues, Switzerland) and ProTaper (VDW, Munich, Germany)-for root canal preparation in primary molars. Materials and Methods: India ink was injected to 160 mesiobucca...

  16. Aircraft noise prediction program theoretical manual: Rotorcraft System Noise Prediction System (ROTONET), part 4

    Science.gov (United States)

    Weir, Donald S.; Jumper, Stephen J.; Burley, Casey L.; Golub, Robert A.

    1995-01-01

    This document describes the theoretical methods used in the rotorcraft noise prediction system (ROTONET), which is a part of the NASA Aircraft Noise Prediction Program (ANOPP). The ANOPP code consists of an executive, database manager, and prediction modules for jet engine, propeller, and rotor noise. The ROTONET subsystem contains modules for the prediction of rotor airloads and performance with momentum theory and prescribed wake aerodynamics, rotor tone noise with compact chordwise and full-surface solutions to the Ffowcs-Williams-Hawkings equations, semiempirical airfoil broadband noise, and turbulence ingestion broadband noise. Flight dynamics, atmosphere propagation, and noise metric calculations are covered in NASA TM-83199, Parts 1, 2, and 3.

  17. Wind Systems for Pumping Water: A Training Manual. No. T-25.

    Science.gov (United States)

    Eschenbach, Willis

    This document was prepared as a training manual for people interested in developing appropriate technological approaches to using wind power to pump water. The training program is divided into two basic formats, one in which a session focuses on the design process and participants are expected to do some design work in groups, and another which…

  18. Comparing Whole Building Energy Implications of Sidelighting Systems with Alternate Manual Blind Control Algorithms

    Directory of Open Access Journals (Sweden)

    Christopher Dyke

    2015-05-01

    Full Text Available Currently, there is no manual blind control guideline used consistently throughout the energy modeling community. This paper identifies and compares five manual blind control algorithms with unique control patterns and reports blind occlusion, rate of change data, and annual building energy consumption. The blind control schemes detailed here represent five reasonable candidates for use in lighting and energy simulation based on difference driving factors. This study was performed on a medium-sized office building using EnergyPlus with the internal daylight harvesting engine. Results show that applying manual blind control algorithms affects the total annual consumption of the building by as much as 12.5% and 11.5% for interior and exterior blinds respectively, compared to the Always Retracted blinds algorithm. Peak demand was also compared showing blind algorithms affected zone load sizing by as much as 9.8%. The alternate algorithms were tested for their impact on American Society of Heating, Refrigeration and Air-Conditioning Engineers (ASHRAE Guideline 14 calibration metrics and all models were found to differ from the original calibrated baseline by more than the recommended ±15% for coefficient of variance of the mean square error (CVRMSE and ±5% for normalized mean bias error (NMBE. The paper recommends that energy modelers use one or more manual blind control algorithms during design stages when making decisions about energy efficiency and other design alternatives.

  19. Creating a systems engineering approach for the manual on uniform traffic control devices.

    Science.gov (United States)

    2011-03-01

    The Manual on Uniform Traffic Control Devices (MUTCD) provides basic principles for use of traffic : control devices (TCD). However, most TCDs are not explicitly required, and the decision to use a given : TCD in a given situation is typically made b...

  20. Structures manual

    Science.gov (United States)

    2001-01-01

    This manual was written as a guide for use by design personnel in the Vermont Agency of Transportation Structures Section. This manual covers the design responsibilities of the Section. It does not cover other functions that are a part of the Structu...

  1. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    International Nuclear Information System (INIS)

    Kumada, Hiroaki; Torii, Yoshiya

    2002-09-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

  2. ELCOS: the PSI code system for LWR core analysis. Part II: user's manual for the fuel assembly code BOXER

    International Nuclear Information System (INIS)

    Paratte, J.M.; Grimm, P.; Hollard, J.M.

    1996-02-01

    ELCOS is a flexible code system for the stationary simulation of light water reactor cores. It consists of the four computer codes ETOBOX, BOXER, CORCOD and SILWER. The user's manual of the second one is presented here. BOXER calculates the neutronics in cartesian geometry. The code can roughly be divided into four stages: - organisation: choice of the modules, file manipulations, reading and checking of input data, - fine group fluxes and condensation: one-dimensional calculation of fluxes and computation of the group constants of homogeneous materials and cells, - two-dimensional calculations: geometrically detailed simulation of the configuration in few energy groups, - burnup: evolution of the nuclide densities as a function of time. This manual shows all input commands which can be used while running the different modules of BOXER. (author) figs., tabs., refs

  3. Manual and automatic locomotion scoring systems in dairy cows: a review.

    Science.gov (United States)

    Schlageter-Tello, Andrés; Bokkers, Eddie A M; Koerkamp, Peter W G Groot; Van Hertem, Tom; Viazzi, Stefano; Romanini, Carlos E B; Halachmi, Ilan; Bahr, Claudia; Berckmans, Daniël; Lokhorst, Kees

    2014-09-01

    The objective of this review was to describe, compare and evaluate agreement, reliability, and validity of manual and automatic locomotion scoring systems (MLSSs and ALSSs, respectively) used in dairy cattle lameness research. There are many different types of MLSSs and ALSSs. Twenty-five MLSSs were found in 244 articles. MLSSs use different types of scale (ordinal or continuous) and different gait and posture traits need to be observed. The most used MLSS (used in 28% of the references) is based on asymmetric gait, reluctance to bear weight, and arched back, and is scored on a five-level scale. Fifteen ALSSs were found that could be categorized according to three approaches: (a) the kinetic approach measures forces involved in locomotion, (b) the kinematic approach measures time and distance of variables associated to limb movement and some specific posture variables, and (c) the indirect approach uses behavioural variables or production variables as indicators for impaired locomotion. Agreement and reliability estimates were scarcely reported in articles related to MLSSs. When reported, inappropriate statistical methods such as PABAK and Pearson and Spearman correlation coefficients were commonly used. Some of the most frequently used MLSSs were poorly evaluated for agreement and reliability. Agreement and reliability estimates for the original four-, five- or nine-level MLSS, expressed in percentage of agreement, kappa and weighted kappa, showed large ranges among and sometimes also within articles. After the transformation into a two-level scale, agreement and reliability estimates showed acceptable estimates (percentage of agreement ≥ 75%; kappa and weighted kappa ≥ 0.6), but still estimates showed a large variation between articles. Agreement and reliability estimates for ALSSs were not reported in any article. Several ALSSs use MLSSs as a reference for model calibration and validation. However, varying agreement and reliability estimates of MLSSs make a

  4. Guidelines for the verification and validation of expert system software and conventional software: User`s manual. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A. [Science Applications International Corp., McLean, VA (United States)

    1995-03-01

    This report provides a step-by-step guide, or user manual, for personnel responsible for the planning and execution of the verification and validation (V&V), and developmental testing, of expert systems, conventional software systems, and various other types of artificial intelligence systems. While the guide was developed primarily for applications in the utility industry, it applies well to all industries. The user manual has three sections. In Section 1 the user assesses the stringency of V&V needed for the system under consideration, identifies the development stage the system is in, and identifies the component(s) of the system to be tested next. These three pieces of information determine which Guideline Package of V&V methods is most appropriate for those conditions. The V&V Guideline Packages are provided in Section 2. Each package consists of an ordered set of V&V techniques to be applied to the system, guides on choosing the review/evaluation team, measurement criteria, and references to a book or report which describes the application of the method. Section 3 presents details of 11 of the most important (or least well-explained in the literature) methods to assist the user in applying these techniques accurately.

  5. Guidelines for the verification and validation of expert system software and conventional software: User's manual. Volume 7

    International Nuclear Information System (INIS)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A.

    1995-03-01

    This report provides a step-by-step guide, or user manual, for personnel responsible for the planning and execution of the verification and validation (V ampersand V), and developmental testing, of expert systems, conventional software systems, and various other types of artificial intelligence systems. While the guide was developed primarily for applications in the utility industry, it applies well to all industries. The user manual has three sections. In Section 1 the user assesses the stringency of V ampersand V needed for the system under consideration, identifies the development stage the system is in, and identifies the component(s) of the system to be tested next. These three pieces of information determine which Guideline Package of V ampersand V methods is most appropriate for those conditions. The V ampersand V Guideline Packages are provided in Section 2. Each package consists of an ordered set of V ampersand V techniques to be applied to the system, guides on choosing the review/evaluation team, measurement criteria, and references to a book or report which describes the application of the method. Section 3 presents details of 11 of the most important (or least well-explained in the literature) methods to assist the user in applying these techniques accurately

  6. California Publicly-Owned Utilities (POUs) – LBNL ‘Beyond Widgets’ Project. Task: ambient lighting and occupancy-based plug load control. System Program Manual

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Alastair; Mathew, Paul A.; Regnier, Cynthia; Schwartz, Peter; Schakelford, Jordan; Walter, Travis

    2017-09-01

    This program manual contains detailed technical information for implementing an incentive program for task-ambient lighting and occupancy-based plug load control. This manual was developed by Lawrence Berkeley National Laboratory, in collaboration with the California Publicly-Owned Utilities (CA POUs) as a partner in the ‘Beyond Widgets’ program funded by the U.S. Department of Energy Building Technologies Office. The primary audience for this manual is the program staff of the various CA POUs. It may also be used by other utility incentive programs to help develop similar programs. It is anticipated that the content of this manual be utilized by the CA POU staff for developing related documents such as the Technical Resource Manual and other filings pertaining to the rollout of an energy systems-based rebate incentive program.

  7. WHO basic radiological system: Manual of radiographic interpretation for general practitioners

    International Nuclear Information System (INIS)

    Palmer, P.E.S.; Cockshott, W.P.; Hegedus, V.; Samuel, E.

    1985-01-01

    This manual serves as a guide to basic radiologic procedures such as chest, abdominal, and skeletal examinations as well as simple nonfluoroscopic studies using contrast material. The book concentrates on the more common diagnostic problems encountered in medicine, as the services of a radiologist would be required for the more complicated techniques. The text begins with a short introductory note describing the intentions of the manual and the goals of the BRS. Following this, there are several complete sections covering essential areas in radiology. The first section, on radiation risks and protective countermeasures, serves to instruct radiologic personnel concisely on how to minimize their exposure to the harmful effects of radiation. In the second section, adverse reactions to intravenous drugs used in urography are described, and the appropriate treatment for such reactions are outlined. Following this, proper patient care and first-aid measures to be employed in the event of an emergency are described in several pages

  8. WHO basic radiological system: Manual of radiographic interpretation for general practitioners

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, P.E.S.; Cockshott, W.P.; Hegedus, V.; Samuel, E.

    1985-01-01

    This manual serves as a guide to basic radiologic procedures such as chest, abdominal, and skeletal examinations as well as simple nonfluoroscopic studies using contrast material. The book concentrates on the more common diagnostic problems encountered in medicine, as the services of a radiologist would be required for the more complicated techniques. The text begins with a short introductory note describing the intentions of the manual and the goals of the BRS. Following this, there are several complete sections covering essential areas in radiology. The first section, on radiation risks and protective countermeasures, serves to instruct radiologic personnel concisely on how to minimize their exposure to the harmful effects of radiation. In the second section, adverse reactions to intravenous drugs used in urography are described, and the appropriate treatment for such reactions are outlined. Following this, proper patient care and first-aid measures to be employed in the event of an emergency are described in several pages.

  9. Digital VLSI systems design a design manual for implementation of projects on FPGAs and ASICs using Verilog

    CERN Document Server

    Ramachandran, S

    2007-01-01

    Digital VLSI Systems Design is written for an advanced level course using Verilog and is meant for undergraduates, graduates and research scholars of Electrical, Electronics, Embedded Systems, Computer Engineering and interdisciplinary departments such as Bio Medical, Mechanical, Information Technology, Physics, etc. It serves as a reference design manual for practicing engineers and researchers as well. Diligent freelance readers and consultants may also start using this book with ease. The book presents new material and theory as well as synthesis of recent work with complete Project Designs

  10. Exposure to Inhalable Dust, Endotoxin, and Total Volatile Organic Carbons on Dairy Farms Using Manual and Automated Feeding Systems

    DEFF Research Database (Denmark)

    Basinas, Ioannis; Cronin, Garvin; Hogan, Victoria

    2017-01-01

    Introduction: Agricultural workers tend to have high exposures to organic dusts which may induce or exacerbate respiratory disorders. Studies investigating the effect of work tasks and farm characteristics on organic dust exposures among farm workers suggest that handling of animal feed is an imp...... feeding. Until effective permanent engineering controls are established farm workers should be encouraged to wear respiratory protective equipment during these tasks....... of exposure to these agents depend on the applied feeding system in the farms. Methods: Thirty-eight personal exposure measurements were collected from farmers across seven dairy farms. The farms used manual, loft, or semi-automated feeding systems. Information on worker tasks and farm characteristics...

  11. Sensitometric comparison of E and F dental radiographic films using manual and automatic processing systems

    Directory of Open Access Journals (Sweden)

    Dabaghi A.

    2008-04-01

    Full Text Available Background and Aim: Processing conditions affect sensitometric properties of X-ray films. In this study, we aimed to evaluate the sensitometric characteristics of InSight (IP, a new F-speed film, in fresh and used processing solutions in dental office condition and compare them with Ektaspeed Plus (EP.Materials and Methods: In this experimental in vitro study, an aluminium step wedge was used to construct characteristic curves for InSight and Ektaspeed Plus films (Kodak Eastman, Rochester, USA.All films were processed in Champion solution (X-ray Iran, Tehran, Iran both manually and automatically in a period of six days. Unexposed films of both types were processed manually and automatically to determine base plus fog density. Speed and film contrast were measured according to ISO definition. Data were analyzed using one-way ANOVA and T tests with P<0.05 as the level of significance.Results: IP was 20 to 22% faster than EP and showed to be an F-speed film when processed in automatic condition and E-F film when processed manually. Also it was F-speed in fresh solution and E-speed in old solution. IP and EP contrasts were similar in automatic processing but EP contrast was higher when processed manually. Both EP and IP films had standard values of base plus fog (<0.35 and B+F densities were decreased in old solution.Conclusion: Based on the results of this study, InSight is a F-speed film with a speed of at least 20% greater than Ektaspeed. In addition, it reduces patient exposure with no damage to image quality.

  12. Comparison of QIAsymphony Automated and QIAamp Manual DNA Extraction Systems for Measuring Epstein-Barr Virus DNA Load in Whole Blood Using Real-Time PCR

    OpenAIRE

    Laus, Stella; Kingsley, Lawrence A.; Green, Michael; Wadowsky, Robert M.

    2011-01-01

    Automated and manual extraction systems have been used with real-time PCR for quantification of Epstein-Barr virus [human herpesvirus 4 (HHV-4)] DNA in whole blood, but few studies have evaluated relative performances. In the present study, the automated QIAsymphony and manual QIAamp extraction systems (Qiagen, Valencia, CA) were assessed using paired aliquots derived from clinical whole-blood specimens and an in-house, real-time PCR assay. The detection limits using the QIAsymphony and QIAam...

  13. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  14. GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

  15. GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-11-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

  16. ERWIN2: User's manual for a computer model to calculate the economic efficiency of wind energy systems

    International Nuclear Information System (INIS)

    Van Wees, F.G.H.

    1992-01-01

    During the last few years the Business Unit ESC-Energy Studies of the Netherlands Energy Research Foundation (ECN) developed calculation programs to determine the economic efficiency of energy technologies, which programs support several studies for the Dutch Ministry of Economic Affairs. All these programs form the so-called BRET programs. One of these programs is ERWIN (Economische Rentabiliteit WINdenergiesystemen or in English: Economic Efficiency of Wind Energy Systems) of which an updated manual (ERWIN2) is presented in this report. An outline is given of the possibilities and limitations to carry out calculations with the model

  17. Fiscal 1997 survey report. Preparatory survey for a manual on the introduction of high efficiency thermal utilization systems; 1997 nendo chosa hokokusho. Kokoritsu netsu riyo system donyu manual no sakusei choa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    To cope with the energy issue and global environmental issue, it is necessary to forcibly promote energy conservation. In the light of the present situation that in Japan only 1/3 of the primary energy consumed is effectively used, policies are being prepared for promotion of the introduction of high efficiency thermal utilization systems including `a project for formation of the environmentally friendly type energy community` promoted by NEDO. However, it is hard to say that the introduction is being actively promoted. The cause is that they do not fully understood the present status of high efficiency thermal utilization systems, procedures for introduction, subsidy system, etc. Therefore, a manual was made to present to self governments and enterprisers who are planning to introduce the system. To be concrete, there are the six systems: cogeneration use thermal supply system, unused energy use thermal supply system, heat storage use thermal supply system, waste use thermal supply system, plant surplus energy use thermal supply system, and cascade type thermal supply system. 28 refs., 38 figs., 42 tabs.

  18. Cleaning capacity promoted by motor-driven or manual instrumentation using ProTaper Universal system: Histological analysis.

    Science.gov (United States)

    da Frota, Matheus Franco; Filho, Idomeo Bonetti; Berbert, Fábio Luiz Camargo Villela; Sponchiado, Emilio Carlos; Marques, André Augusto Franco; Garcia, Lucas da Fonseca Roberti

    2013-01-01

    The aim of this study was to assess the cleaning capacity of the Protaper system using motor-driven or manual instrumentation. Ten mandibular molars were randomly separated into 2 groups (n = 5) according to the type of instrumentation performed, as follows: Group 1 - instrumentation with rotary nickel-titanium (Ni-Ti) files using ProTaper Universal System (Dentsply/Maillefer); and, Group 2 - instrumentation with Ni-Ti hand files using ProTaper Universal (Dentsply-Maillefer). Afterwards, the teeth were sectioned transversely and submitted to histotechnical processing to obtain histological sections for microscopic evaluation. The images were analyzed by the Corel Photo-Paint X5 program (Corel Corporation) using an integration grid superimposed on the image. Statistical analysis (U-Mann-Whitney - P < 0.05) demonstrated that G1 presented higher cleaning capacity when compared to G2. The rotary technique presented better cleaning results in the apical third of the root canal system when compared to the manual technique.

  19. Manual versus Automated Rodent Behavioral Assessment: Comparing Efficacy and Ease of Bederson and Garcia Neurological Deficit Scores to an Open Field Video-Tracking System

    OpenAIRE

    Fiona A. Desland; Aqeela Afzal; Zuha Warraich; J Mocco

    2014-01-01

    Animal models of stroke have been crucial in advancing our understanding of the pathophysiology of cerebral ischemia. Currently, the standards for determining neurological deficit in rodents are the Bederson and Garcia scales, manual assessments scoring animals based on parameters ranked on a narrow scale of severity. Automated open field analysis of a live-video tracking system that analyzes animal behavior may provide a more sensitive test. Results obtained from the manual Bederson and Garc...

  20. Coulometer operator's manual

    International Nuclear Information System (INIS)

    Criscuolo, A.L.

    1977-07-01

    The coulometer control system automates the titration of uranium and plutonium as performed by the CMB-1 group. The system consists of a printer, microcontroller, and coulometer, all of which are controlled by an algorithm stored in the microcontroller read-only memory. This manual describes the titration procedure using the coulometer control system, its theory and maintenance

  1. Biosafety Manual

    Energy Technology Data Exchange (ETDEWEB)

    King, Bruce W.

    2010-05-18

    Work with or potential exposure to biological materials in the course of performing research or other work activities at Lawrence Berkeley National Laboratory (LBNL) must be conducted in a safe, ethical, environmentally sound, and compliant manner. Work must be conducted in accordance with established biosafety standards, the principles and functions of Integrated Safety Management (ISM), this Biosafety Manual, Chapter 26 (Biosafety) of the Health and Safety Manual (PUB-3000), and applicable standards and LBNL policies. The purpose of the Biosafety Program is to protect workers, the public, agriculture, and the environment from exposure to biological agents or materials that may cause disease or other detrimental effects in humans, animals, or plants. This manual provides workers; line management; Environment, Health, and Safety (EH&S) Division staff; Institutional Biosafety Committee (IBC) members; and others with a comprehensive overview of biosafety principles, requirements from biosafety standards, and measures needed to control biological risks in work activities and facilities at LBNL.

  2. MARS CODE MANUAL VOLUME III - Programmer's Manual

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Hwang, Moon Kyu; Jeong, Jae Jun; Kim, Kyung Doo; Bae, Sung Won; Lee, Young Jin; Lee, Won Jae

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This programmer's manual provides a complete list of overall information of code structure and input/output function of MARS. In addition, brief descriptions for each subroutine and major variables used in MARS are also included in this report, so that this report would be very useful for the code maintenance. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  3. User's Manual for the Naval Interactive Data Analysis System-Climatologies (NIDAS-C), Version 2.0

    Science.gov (United States)

    Abbott, Clifton

    1996-01-01

    This technical note provides the user's manual for the NIDAS-C system developed for the naval oceanographic office. NIDAS-C operates using numerous oceanographic data categories stored in an installed version of the Naval Environmental Operational Nowcast System (NEONS), a relational database management system (rdbms) which employs the ORACLE proprietary rdbms engine. Data management, configuration, and control functions for the supporting rdbms are performed externally. NIDAS-C stores and retrieves data to/from the rdbms but exercises no direct internal control over the rdbms or its configuration. Data is also ingested into the rdbms, for use by NIDAS-C, by external data acquisition processes. The data categories employed by NIDAS-C are as follows: Bathymetry - ocean depth at

  4. Comparison of CT Fluoroscopy-Guided Manual and CT-Guided Robotic Positioning System for In Vivo Needle Placements in Swine Liver

    Energy Technology Data Exchange (ETDEWEB)

    Cornelis, F.; Takaki, H. [Memorial Sloan-Kettering Cancer Center, Interventional Radiology Service, Department of Radiology (United States); Laskhmanan, M. [Perfint Healthcare Inc (India); Durack, J. C.; Erinjeri, J. P.; Getrajdman, G. I.; Maybody, M.; Sofocleous, C. T.; Solomon, S. B.; Srimathveeravalli, G., E-mail: srimaths@mskcc.org [Memorial Sloan-Kettering Cancer Center, Interventional Radiology Service, Department of Radiology (United States)

    2015-10-15

    PurposeTo compare CT fluoroscopy-guided manual and CT-guided robotic positioning system (RPS)-assisted needle placement by experienced IR physicians to targets in swine liver.Materials and MethodsManual and RPS-assisted needle placement was performed by six experienced IR physicians to four 5 mm fiducial seeds placed in swine liver (n = 6). Placement performance was assessed for placement accuracy, procedure time, number of confirmatory scans, needle manipulations, and procedure radiation dose. Intra-modality difference in performance for each physician was assessed using paired t test. Inter-physician performance variation for each modality was analyzed using Kruskal–Wallis test.ResultsPaired comparison of manual and RPS-assisted placements to a target by the same physician indicated accuracy outcomes was not statistically different (manual: 4.53 mm; RPS: 4.66 mm; p = 0.41), but manual placement resulted in higher total radiation dose (manual: 1075.77 mGy/cm; RPS: 636.4 mGy/cm; p = 0.03), required more confirmation scans (manual: 6.6; RPS: 1.6; p < 0.0001) and needle manipulations (manual: 4.6; RPS: 0.4; p < 0.0001). Procedure time for RPS was longer than manual placement (manual: 6.12 min; RPS: 9.7 min; p = 0.0003). Comparison of inter-physician performance during manual placement indicated significant differences in the time taken to complete placements (p = 0.008) and number of repositions (p = 0.04) but not in other study measures (p > 0.05). Comparison of inter-physician performance during RPS-assisted placement suggested statistically significant differences in procedure time (p = 0.02) and not in other study measures (p > 0.05).ConclusionsCT-guided RPS-assisted needle placement reduced radiation dose, number of confirmatory scans, and needle manipulations when compared to manual needle placement by experienced IR physicians, with equivalent accuracy.

  5. Comparison of CT Fluoroscopy-Guided Manual and CT-Guided Robotic Positioning System for In Vivo Needle Placements in Swine Liver

    International Nuclear Information System (INIS)

    Cornelis, F.; Takaki, H.; Laskhmanan, M.; Durack, J. C.; Erinjeri, J. P.; Getrajdman, G. I.; Maybody, M.; Sofocleous, C. T.; Solomon, S. B.; Srimathveeravalli, G.

    2015-01-01

    PurposeTo compare CT fluoroscopy-guided manual and CT-guided robotic positioning system (RPS)-assisted needle placement by experienced IR physicians to targets in swine liver.Materials and MethodsManual and RPS-assisted needle placement was performed by six experienced IR physicians to four 5 mm fiducial seeds placed in swine liver (n = 6). Placement performance was assessed for placement accuracy, procedure time, number of confirmatory scans, needle manipulations, and procedure radiation dose. Intra-modality difference in performance for each physician was assessed using paired t test. Inter-physician performance variation for each modality was analyzed using Kruskal–Wallis test.ResultsPaired comparison of manual and RPS-assisted placements to a target by the same physician indicated accuracy outcomes was not statistically different (manual: 4.53 mm; RPS: 4.66 mm; p = 0.41), but manual placement resulted in higher total radiation dose (manual: 1075.77 mGy/cm; RPS: 636.4 mGy/cm; p = 0.03), required more confirmation scans (manual: 6.6; RPS: 1.6; p < 0.0001) and needle manipulations (manual: 4.6; RPS: 0.4; p < 0.0001). Procedure time for RPS was longer than manual placement (manual: 6.12 min; RPS: 9.7 min; p = 0.0003). Comparison of inter-physician performance during manual placement indicated significant differences in the time taken to complete placements (p = 0.008) and number of repositions (p = 0.04) but not in other study measures (p > 0.05). Comparison of inter-physician performance during RPS-assisted placement suggested statistically significant differences in procedure time (p = 0.02) and not in other study measures (p > 0.05).ConclusionsCT-guided RPS-assisted needle placement reduced radiation dose, number of confirmatory scans, and needle manipulations when compared to manual needle placement by experienced IR physicians, with equivalent accuracy

  6. Broadband Fan Noise Prediction System for Turbofan Engines. Volume 1; Setup_BFaNS User's Manual and Developer's Guide

    Science.gov (United States)

    Morin, Bruce L.

    2010-01-01

    Pratt & Whitney has developed a Broadband Fan Noise Prediction System (BFaNS) for turbofan engines. This system computes the noise generated by turbulence impinging on the leading edges of the fan and fan exit guide vane, and noise generated by boundary-layer turbulence passing over the fan trailing edge. BFaNS has been validated on three fan rigs that were tested during the NASA Advanced Subsonic Technology Program (AST). The predicted noise spectra agreed well with measured data. The predicted effects of fan speed, vane count, and vane sweep also agreed well with measurements. The noise prediction system consists of two computer programs: Setup_BFaNS and BFaNS. Setup_BFaNS converts user-specified geometry and flow-field information into a BFaNS input file. From this input file, BFaNS computes the inlet and aft broadband sound power spectra generated by the fan and FEGV. The output file from BFaNS contains the inlet, aft and total sound power spectra from each noise source. This report is the first volume of a three-volume set documenting the Broadband Fan Noise Prediction System: Volume 1: Setup_BFaNS User s Manual and Developer s Guide; Volume 2: BFaNS User's Manual and Developer s Guide; and Volume 3: Validation and Test Cases. The present volume begins with an overview of the Broadband Fan Noise Prediction System, followed by step-by-step instructions for installing and running Setup_BFaNS. It concludes with technical documentation of the Setup_BFaNS computer program.

  7. Broadband Fan Noise Prediction System for Turbofan Engines. Volume 2; BFaNS User's Manual and Developer's Guide

    Science.gov (United States)

    Morin, Bruce L.

    2010-01-01

    Pratt & Whitney has developed a Broadband Fan Noise Prediction System (BFaNS) for turbofan engines. This system computes the noise generated by turbulence impinging on the leading edges of the fan and fan exit guide vane, and noise generated by boundary-layer turbulence passing over the fan trailing edge. BFaNS has been validated on three fan rigs that were tested during the NASA Advanced Subsonic Technology Program (AST). The predicted noise spectra agreed well with measured data. The predicted effects of fan speed, vane count, and vane sweep also agreed well with measurements. The noise prediction system consists of two computer programs: Setup_BFaNS and BFaNS. Setup_BFaNS converts user-specified geometry and flow-field information into a BFaNS input file. From this input file, BFaNS computes the inlet and aft broadband sound power spectra generated by the fan and FEGV. The output file from BFaNS contains the inlet, aft and total sound power spectra from each noise source. This report is the second volume of a three-volume set documenting the Broadband Fan Noise Prediction System: Volume 1: Setup_BFaNS User s Manual and Developer s Guide; Volume 2: BFaNS User s Manual and Developer s Guide; and Volume 3: Validation and Test Cases. The present volume begins with an overview of the Broadband Fan Noise Prediction System, followed by step-by-step instructions for installing and running BFaNS. It concludes with technical documentation of the BFaNS computer program.

  8. SNL Abuse Testing Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Orendorff, Christopher [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lamb, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Steele, Leigh Anna Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    This report describes recommended abuse testing procedures for rechargeable energy storage systems (RESSs) for electric vehicles. This report serves as a revision to the FreedomCAR Electrical Energy Storage System Abuse Test Manual for Electric and Hybrid Electric Vehicle Applications (SAND2005-3123).

  9. IAC user manual

    Science.gov (United States)

    Vos, R. G.; Beste, D. L.; Gregg, J.

    1984-01-01

    The User Manual for the Integrated Analysis Capability (IAC) Level 1 system is presented. The IAC system currently supports the thermal, structures, controls and system dynamics technologies, and its development is influenced by the requirements for design/analysis of large space systems. The system has many features which make it applicable to general problems in engineering, and to management of data and software. Information includes basic IAC operation, executive commands, modules, solution paths, data organization and storage, IAC utilities, and module implementation.

  10. DIAGNOSTIC CARDIAC CATHETERIZATION USING THE MEDRAD AVANTA FLUID MANAGEMENT SYSTEM AS COMPARED TO THE TRADITIONAL MANUAL INJECTION METHOD

    Energy Technology Data Exchange (ETDEWEB)

    Winniford, Michael D

    2013-02-08

    Nearly 4 million patient procedures performed annually in US cardiac catheterization laboratories utilize contrast media to achieve vessel opacification. The amount of contrast media used is variable and depends on the complexity of the procedure, the method of contrast delivery as well as the skill-level of the operator. Since the total amount of contrast used for each procedure can have both patient safety and economic implications, it is essential for cardiologists to have the ability to control contrast delivery such that optimal angiographic image quality is achieved using the least amount of contrast. Although the complication rate associated with cardiac catheterization remains low, the most common serious complication, contrast-induced nephropathy (CIN), is associated with poor prognosis and a high mortality rate. Numerous interventional strategies for preventing and reducing the severity of CIN have demonstrated varying degrees of clinical benefit, but none has been shown to reliably prevent this serious complication. To date, the most effective approach for reducing the risk of CIN is to properly hydrate the patient and to minimize the amount of contrast media administered. Automated injection systems are intended for use in virtually all cardiac catheterization procedures and have numerous features which can provide potential advantages over traditional methods. With automated injection technology the operator is able to control and precisely monitor contrast delivery. Additionally, the MEDRAD Avanta Fluid Management Injection System utilizes a sterile contrast reservoir which eliminates the need to discard unused contrast in individual opened containers following each procedure. Considering that an average of 50% of opened contrast media is wasted using manual injection methods, this savings can provide a substantial economic benefit. Automated systems also facilitate the use of smaller (5 French) catheter sizes. Precise flow control and the use of

  11. Radar and ARPA manual

    CERN Document Server

    Bole, A G

    2013-01-01

    Radar and ARPA Manual focuses on the theoretical and practical aspects of electronic navigation. The manual first discusses basic radar principles, including principles of range and bearing measurements and picture orientation and presentation. The text then looks at the operational principles of radar systems. Function of units; aerial, receiver, and display principles; transmitter principles; and sitting of units on board ships are discussed. The book also describes target detection, Automatic Radar Plotting Aids (ARPA), and operational controls of radar systems, and then discusses radar plo

  12. The reliability of manual reporting of clinical events in an anesthesia information management system (AIMS).

    Science.gov (United States)

    Simpao, Allan F; Pruitt, Eric Y; Cook-Sather, Scott D; Gurnaney, Harshad G; Rehman, Mohamed A

    2012-12-01

    Manual incident reports significantly under-report adverse clinical events when compared with automated recordings of intraoperative data. Our goal was to determine the reliability of AIMS and CQI reports of adverse clinical events that had been witnessed and recorded by research assistants. The AIMS and CQI records of 995 patients aged 2-12 years were analyzed to determine if anesthesia providers had properly documented the emesis events that were observed and recorded by research assistants who were present in the operating room at the time of induction. Research assistants recorded eight cases of emesis during induction that were confirmed with the attending anesthesiologist at the time of induction. AIMS yielded a sensitivity of 38 % (95 % confidence interval [CI] 8.5-75.5 %), while the sensitivity of CQI reporting was 13 % (95 % CI 0.3-52.7 %). The low sensitivities of the AIMS and CQI reports suggest that user-reported AIMS and CQI data do not reliably include significant clinical events.

  13. The INPRO Methodology and Collaborative Projects related to Fast Reactor Cooling

    International Nuclear Information System (INIS)

    Meyer, L.; Beatty, R.; Gowin, P.; Depisch, F.; Korinny, A.; Villabilbre, P.

    2012-01-01

    Summary of key rusults: → Primary temperatures not significantly changed by: • Delay in initiation of DHR system; • Replacement of sodium by NaK in DHR system; • Decrease in AHX air inlet temperature. → Secondary sodium inventory plays an important role in reducing primary T (~50 K); • The effect of IWF heat transfer on primary temperatures is limited: ~20 K in the fissile core and ~50 K in the blanket zone. CP outcome: International cooperation in safety aspects of FR design development: • Shared information on FR design characteristics and performance; • Motivated code development, sharing code characteristics, modelling approaches and calculation results; • Identified relevant areas for further international cooperation

  14. Summary of the 11-th session of the AER Working Group F - 'Spent Fuel transmutations' and 2nd meeting of INPRO Project RMI - 'Meeting energy needs in the period of raw materials insufficiency during the 21st century'

    International Nuclear Information System (INIS)

    Lelek, V.

    2009-01-01

    There was concluded on the session during discussion, that we must be very cautious in giving forecast of particular form of energy demand and that any longer development in energy is no more possible without taking into account boundary conditions in oil and gas external supply. It was recommended in the discussion to prepare publication based on works, which were published, and try to give into it formulation of new tasks as in nuclear technologies so from nonnuclear branches, including possible society feedbacks. There were several works on the meeting concerning fluoride technology application for future more effective and cleaner reprocessing of spent nuclear fuel. It must be noted that participants expect that it will be part of new technology development, which of course must be done in greater capacities and in more direct connections with new preindustrial project. Such development is expected. It was also discussed how to proceed with INPRO publication 'Task 3 - Global vision of nuclear energy in the 21st century' - up to now the text is prepared in different ways - our position that expected troubles and at least qualitative recommendations for future steps should be there reflected. The technical program covered also the following topics: System energy research in RRC Kurchatov Institute; Results of program SPHINX; Energy forecasts: Methods and computer codes; Preliminary results of analysis of energy situation in the Central Europe; Perspectives of Molten Salt Reactor development in Czech Republic; Calculations of operation states of packed distillation column for uranium hexafluoride; Neutronic Analysis of Two-Fluid Thorium Molten Salt Reactor; Cross-section Measurements of (n,xn) Reactions in the Energy Range 20-100 MeV; The Czech Geological Repository Reference Design 2011: impacts on the strategy of the fuel cycle back end ect.

  15. Metrication manual

    International Nuclear Information System (INIS)

    Harper, A.F.A.; Digby, R.B.; Thong, S.P.; Lacey, F.

    1978-04-01

    In April 1978 a meeting of senior metrication officers convened by the Commonwealth Science Council of the Commonwealth Secretariat, was held in London. The participants were drawn from Australia, Bangladesh, Britain, Canada, Ghana, Guyana, India, Jamaica, Papua New Guinea, Solomon Islands and Trinidad and Tobago. Among other things, the meeting resolved to develop a set of guidelines to assist countries to change to SI and to compile such guidelines in the form of a working manual

  16. Effects of bedding systems selected by manual muscle testing on sleep and sleep-related respiratory disturbances.

    Science.gov (United States)

    Tsai, Ling-Ling; Liu, Hau-Min

    2008-03-01

    In this study, we investigated the feasibility of applying manual muscle testing (MMT) for bedding selection and examined the bedding effect on sleep. Four lay testers with limited training in MMT performed muscle tests for the selection of the bedding systems from five different mattresses and eight different pillows for 14 participants with mild sleep-related respiratory disturbances. For each participant individually, two bedding systems-one inducing stronger muscle forces and the other inducing weaker forces-were selected. The tester-participant pairs showed 85% and 100% agreement, respectively, for the selection of mattresses and pillows that induced the strongest muscle forces. The firmness of the mattress and the height of the pillow were significantly correlated with the body weight and body mass index of the participants for the selected strong bedding system but not for the weak bedding system. Finally, differences were observed between the strong and the weak bedding systems with regard to sleep-related respiratory disturbances and the percentage of slow-wave sleep. It was concluded that MMT can be performed by inexperienced testers for the selection of bedding systems.

  17. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 5.0: Data loading manual. Volume 10

    International Nuclear Information System (INIS)

    VanHorn, R.L.; Wolfram, L.M.; Fowler, R.D.; Beck, S.T.; Smith, C.L.

    1995-04-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) suite of programs can be used to organize and standardize in an electronic format information from probabilistic risk assessments or individual plant examinations. The Models and Results Database (MAR-D) program of the SAPHIRE suite serves as the repository for probabilistic risk assessment and individual plant examination data and information. This report demonstrates by examples the common electronic and manual methods used to load these types of data. It is not a stand alone document but references documents that contribute information relative to the data loading process. This document provides a more detailed discussion and instructions for using SAPHIRE 5.0 only when enough information on a specific topic is not provided by another available source

  18. Solar Powered Aircraft, Photovoltaic Array/Battery System Tabletop Demonstration: Design and Operation Manual

    Science.gov (United States)

    Colozza, Anthony J.; Scheiman, David A.; Bailey, Sheila (Technical Monitor)

    2000-01-01

    A system was constructed to demonstrate the power system operation of a solar powered aircraft. The system consists of a photovoltaic (PV) array, a charge controller, a battery, an electric motor and propeller. The system collects energy from the PV array and either utilizes this energy to operate an electric motor or stores it in a rechargeable battery for future use. The system has a control panel which displays the output of the array and battery as well as the total current going to the electric motor. The control panel also has a means for adjusting the output to the motor to control its speed. The entire system is regulated around 12 VDC.

  19. Safety and Mission Assurance (SMA) Automated Task Order Management System (ATOMS) Operation Manual

    Science.gov (United States)

    Wallace, Shawn; Fikes, Lou A.

    2016-01-01

    This document describes operational aspects of the ATOMS system. The information provided is limited to the functionality provided by ATOMS and does not include information provided in the contractor's proprietary financial and task management system.

  20. Collision avoidance system cost-benefit analysis : volume I - technical manual

    Science.gov (United States)

    1981-09-01

    Collision-avoidance systems under development in the U.S.A., Japan and Germany were evaluated. The performance evaluation showed that the signal processing and the control law of a system were the key parameters that decided the system's capability, ...

  1. Salinas : theory manual.

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, Timothy Francis; Reese, Garth M.; Bhardwaj, Manoj Kumar

    2011-11-01

    Salinas provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of structural systems. This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas, we refer the reader to Salinas, User's Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programmer notes manual, the user's notes and of course the material in the open literature.

  2. Southern Ductile Training Manual.

    Science.gov (United States)

    Alabama State Dept. of Education, Montgomery.

    This instructor's manual contains the materials required to conduct the competency-based workplace literacy program that was developed to help employees at a foundry that has evolved from a small, family-owned business into a major foundry group with several automated production systems. The workplace literacy program consists of 24 lessons in…

  3. NDS EXFOR Manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1979-06-01

    This manual contains the coding rules and formats and NDS internal compilation rules for the exchange format (EXFOR) for the transmission of nuclear reaction data between national and international nuclear data centres, and for the data storage and retrieval system of the IAEA Nuclear Data Section

  4. RRFC hardware operation manual

    International Nuclear Information System (INIS)

    Abhold, M.E.; Hsue, S.T.; Menlove, H.O.; Walton, G.

    1996-05-01

    The Research Reactor Fuel Counter (RRFC) system was developed to assay the 235 U content in spent Material Test Reactor (MTR) type fuel elements underwater in a spent fuel pool. RRFC assays the 235 U content using active neutron coincidence counting and also incorporates an ion chamber for gross gamma-ray measurements. This manual describes RRFC hardware, including detectors, electronics, and performance characteristics

  5. AELIB user's manual

    International Nuclear Information System (INIS)

    Evans, L.E.; Klawitter, G.L.

    1981-05-01

    This report is an updatable manual for users of AELIB, the AECL Library of FORTRAN-callable routines for the CRNL CDC 6600/CYBER 170 system. It provides general advice on the use of this library and detailed information on the selection and usage of particular library routines

  6. Water Quality Monitoring Manual.

    Science.gov (United States)

    Mason, Fred J.; Houdart, Joseph F.

    This manual is designed for students involved in environmental education programs dealing with water pollution problems. By establishing a network of Environmental Monitoring Stations within the educational system, four steps toward the prevention, control, and abatement of water pollution are proposed. (1) Train students to recognize, monitor,…

  7. Users Manual for the FEHMN application

    International Nuclear Information System (INIS)

    Zyvoloski, G.A.; Robinson, B.A.; Dash, Z.V.; Trease, L.L.

    1996-01-01

    The user's manual documents the use of the Yucca Mountain Site Characterization Projects Finite element heat and mass transfer code (FEHMN) application. The manual covers: Program considerations, data files, input data, output, system interface, and examples

  8. User manual of the CATSS system (version 1.0) communication analysis tool for space station

    Science.gov (United States)

    Tsang, C. S.; Su, Y. T.; Lindsey, W. C.

    1983-01-01

    The Communication Analysis Tool for the Space Station (CATSS) is a FORTRAN language software package capable of predicting the communications links performance for the Space Station (SS) communication and tracking (C & T) system. An interactive software package was currently developed to run on the DEC/VAX computers. The CATSS models and evaluates the various C & T links of the SS, which includes the modulation schemes such as Binary-Phase-Shift-Keying (BPSK), BPSK with Direct Sequence Spread Spectrum (PN/BPSK), and M-ary Frequency-Shift-Keying with Frequency Hopping (FH/MFSK). Optical Space Communication link is also included. CATSS is a C & T system engineering tool used to predict and analyze the system performance for different link environment. Identification of system weaknesses is achieved through evaluation of performance with varying system parameters. System tradeoff for different values of system parameters are made based on the performance prediction.

  9. RELAP5/MOD3 code manual: Code structure, system models, and solution methods. Volume 1

    International Nuclear Information System (INIS)

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling, approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. RELAP5/MOD3 code documentation is divided into seven volumes: Volume I provides modeling theory and associated numerical schemes

  10. Standard Technical Manual Identification Numbering System (TMINS). M0000-00-IDX-000 TMINS

    Science.gov (United States)

    1980-05-14

    Systems 2-121 ALIrODIN I INAVMACS. IXS, KRIS. MPDS, CDPS) 2-121 AUTODIN 11 2-021 Shore Automated Systems fNAVCOMPARS, 2-121 NATtO Systems LDMX, IXS...see Table 2-5, Part III.C). a. This method has the following advantages : (1) It will allow the additional or deletion of parts without disrupting the

  11. Users manual data base MATSURV. Reactor pressure vessel material surveillance data management system

    International Nuclear Information System (INIS)

    Kenworthy, L.D.; Tether, C.D.

    1980-02-01

    This Users Guide to the data management system MATSURV has been prepared to assist the user in all facets of the task of processing data related to reactor pressure vessel materials surveillance; preparation of raw data for input, input of data, modification of existing data, retrieval and display of data, and the creation of data reports. MATSURV is structured upon the System 2000 data base management system which is maintained on the IBM 370/168 computer at National Institutes of Health. An overview of System 2000 is provided

  12. Emergency Response Equipment and Related Training: Airborne Radiological Computer System (Model II) user's manual

    International Nuclear Information System (INIS)

    David P. Colton

    2007-01-01

    The materials included in the Airborne Radiological Computer System, Model-II (ARCS-II) were assembled with several considerations in mind. First, the system was designed to measure and record the airborne gamma radiation levels and the corresponding latitude and longitude coordinates, and to provide a first overview look of the extent and severity of an accident's impact. Second, the portable system had to be light enough and durable enough that it could be mounted in an aircraft, ground vehicle, or watercraft. Third, the system must control the collection and storage of the data, as well as provide a real-time display of the data collection results to the operator. The notebook computer and color graphics printer components of the system would only be used for analyzing and plotting the data. In essence, the provided equipment is composed of an acquisition system and an analysis system. The data can be transferred from the acquisition system to the analysis system at the end of the data collection or at some other agreeable time

  13. COST EVALUATION OF AUTOMATED AND MANUAL POST- CONSUMER PLASTIC BOTTLE SORTING SYSTEMS

    Science.gov (United States)

    This project evaluates, on the basis of performance and cost, two Automated BottleSort® sorting systems for post-consumer commingled plastic containers developed by Magnetic Separation Systems. This study compares the costs to sort mixed bales of post-consumer plastic at these t...

  14. Wisconsin System for Instructional Management: Terminal Operator Manual. Practical Paper No. 19.

    Science.gov (United States)

    Bozeman, William C.; And Others

    The Wisconsin System for Instructional Management (WIS-SIM) is a computer managed instruction (CMI) system designed to improve instructional decision making in order to maximize the educational progress of each child while making efficient use of the available human, material, and financial resources within an organizational structure such as the…

  15. ATHENA code manual. Volume 1. Code structure, system models, and solution methods

    International Nuclear Information System (INIS)

    Carlson, K.E.; Roth, P.A.; Ransom, V.H.

    1986-09-01

    The ATHENA (Advanced Thermal Hydraulic Energy Network Analyzer) code has been developed to perform transient simulation of the thermal hydraulic systems which may be found in fusion reactors, space reactors, and other advanced systems. A generic modeling approach is utilized which permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of a complete facility. Several working fluids are available to be used in one or more interacting loops. Different loops may have different fluids with thermal connections between loops. The modeling theory and associated numerical schemes are documented in Volume I in order to acquaint the user with the modeling base and thus aid effective use of the code. The second volume contains detailed instructions for input data preparation

  16. 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

  17. 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.

  18. No specific role for the manual motor system in processing the meanings of words related to the hand

    Directory of Open Access Journals (Sweden)

    Natasha ePostle

    2013-02-01

    Full Text Available The present study explored whether semantic and motor systems are functionally interwoven via the use of a dual-task paradigm. According to embodied language accounts that propose an automatic and necessary involvement of the motor system in conceptual processing, concurrent processing of hand-related information should interfere more with hand movements than processing of unrelated body-part (i.e., foot, mouth information. Across three experiments, 100 right-handed participants performed left- or right-hand tapping movements while repeatedly reading action words related to different body-parts, or different body-part names, in both aloud and silent conditions. Concurrent reading of single words related to specific body-parts, or the same words embedded in sentences differing in syntactic and phonological complexity (to manipulate context-relevant processing, and reading while viewing videos of the actions and body-parts described by the target words (to elicit visuomotor associations all interfered with right-hand but not left-hand tapping rate. However, this motor interference was not affected differentially by hand-related stimuli. Thus, the results provide no support for proposals that body-part specific resources in cortical motor systems are shared between overt manual movements and meaning-related processing of words related to the hand.

  19. SAFSIM theory manual: A computer program for the engineering simulation of flow systems

    Energy Technology Data Exchange (ETDEWEB)

    Dobranich, D.

    1993-12-01

    SAFSIM (System Analysis Flow SIMulator) is a FORTRAN computer program for simulating the integrated performance of complex flow systems. SAFSIM provides sufficient versatility to allow the engineering simulation of almost any system, from a backyard sprinkler system to a clustered nuclear reactor propulsion system. In addition to versatility, speed and robustness are primary SAFSIM development goals. SAFSIM contains three basic physics modules: (1) a fluid mechanics module with flow network capability; (2) a structure heat transfer module with multiple convection and radiation exchange surface capability; and (3) a point reactor dynamics module with reactivity feedback and decay heat capability. Any or all of the physics modules can be implemented, as the problem dictates. SAFSIM can be used for compressible and incompressible, single-phase, multicomponent flow systems. Both the fluid mechanics and structure heat transfer modules employ a one-dimensional finite element modeling approach. This document contains a description of the theory incorporated in SAFSIM, including the governing equations, the numerical methods, and the overall system solution strategies.

  20. SKED software system. Revision D. Time-shared SUPERSKED. Manual 3

    Energy Technology Data Exchange (ETDEWEB)

    Snapper, A.G.; Inglis, G.

    1977-01-01

    A modified version of State Notation was developed for both hardware and software design of laboratory procedures involving control sequences that vary as a function of the behavior of the experimental subjects. The SKED program was refined and integrated into the OS/8 and time-share systems developed by DEC to take advantage of the development of mass-storage devices and the sophistication of the operating system. The current system consists of the mass-storage devices and the sophistication of the operating system. The current system consists of a two-pass compiler with an optional third-pass listing, a set of programs for identifying and merging data acquisition files, and a sophisticated system monitor that can be used to start, stop, load, and modify as many as 12 independent process control and data acquisition procedures. CCL was modified to accept standard DEC Execute, Compile, and Load commands with special switch options to control the compiling of procedures designed in state notation. Three different methods are available to acquire data from as many as 12 independent stations. The system includes a parameter file and dialog that permits the user to configure his system. Four different clocks, the UDC controller, EAE units, line-printers and other specialized devices may be included. The available memory may be partitioned between the process control section and the OS/8 background. Finally, the number of digital input and output interface lines may be assigned to 12 stations in a flexible manner, by means of an interactive dialog. The system can be configured on any BK OS/8 machine or in the background. 44 figures, 28 tables.

  1. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0. Volume 5, Systems Analysis and Risk Assessment (SARA) tutorial manual

    International Nuclear Information System (INIS)

    Sattison, M.B.; Russell, K.D.; Skinner, N.L.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs) primarily for nuclear power plants. This volume is the tutorial manual for the Systems Analysis and Risk Assessment (SARA) System Version 5.0, a microcomputer-based system used to analyze the safety issues of a open-quotes familyclose quotes [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. A series of lessons is provided that guides the user through some basic steps common to most analyses performed with SARA. The example problems presented in the lessons build on one another, and in combination, lead the user through all aspects of SARA sensitivity analysis capabilities

  2. Preliminary test of remote manual instrumentation & control type system for vacuum unit of 350 KeV / 10 mA electron beam machine

    International Nuclear Information System (INIS)

    Sudiyanto

    2003-01-01

    Remote manual instrumentation & control type for vacuum unit of 350 KeV/10 mA Electron Beam Machine is being completed. The system consisting of a remote manual controlled and a remote acquisition system. A remote manual (50 m) controlled is based on the on/off status of 220 Volt terminal supply for pneumatic valves and vacuum pumps, in this case the power supply switch of pneumatic valves and pumps have already been selected On. Remote acquisition of vacuum level can be done by using a CCTV camera which is place in front of the panning gauge and TGP.300 Balzer unit.The CCTV system equipped with 6 cameras, one TV monitor and a multiplexer unit to arranged a selected picture on it. One of the camera was mounted on the rotator unit, it can be controlled (rotating left / right) for different monitoring orientations required by using infrared controller. A trial test of the remote manual control system for vacuum unit of the Electron Beam Machine showed a good performance. (author)

  3. SIMWEST: A simulation model for wind and photovoltaic energy storage systems (CDC user's manual), volume 1

    Science.gov (United States)

    Warren, A. W.; Esinger, A. W.

    1979-01-01

    Procedures are given for using the SIMWEST program on CDC 6000 series computers. This expanded software package includes wind and/or photovoltaic systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel, and pneumatic).

  4. Electromagnetic Systems Effects Database (EMSED). AERO 90, Phase II User's Manual

    National Research Council Canada - National Science Library

    Sawires, Kalim

    1998-01-01

    The Electromagnetic Systems Effects Database (EMSED), also called AIRBASE, is a training guide for users not familiar with the AIRBASE database and its operating platform, the Macintosh computer (Mac...

  5. User's manual for computer code SOLTES-1 (simulator of large thermal energy systems)

    International Nuclear Information System (INIS)

    Fewell, M.E.; Grandjean, N.R.; Dunn, J.C.; Edenburn, M.W.

    1978-09-01

    SOLTES simulates the steady-state response of thermal energy systems to time-varying data such as weather and loads. Thermal energy system models of both simple and complex systems can easily be modularly constructed from a library of routines. These routines mathematically model solar collectors, pumps, switches, thermal energy storage, thermal boilers, auxiliary boilers, heat exchangers, extraction turbines, extraction turbine/generators, condensers, regenerative heaters, air conditioners, heating and cooling of buildings, process vapor, etc.; SOLTES also allows user-supplied routines. The analyst need only specify fluid names to obtain readout of property data for heat-transfer fluids and constants that characterize power-cycle working fluids from a fluid property data bank. A load management capability allows SOLTES to simulate total energy systems that simultaneously follow heat and power loads and demands. Generalized energy accounting is available, and values for system performance parameters may be automatically determined by SOLTES. Because of its modularity and flexibility, SOLTES can be used to simulate a wide variety of thermal energy systems such as solar power/total energy, fossil fuel power plants/total energy, nuclear power plants/total energy, solar energy heating and cooling, geothermal energy, and solar hot water heaters

  6. Auxiliary mine ventilation manual

    International Nuclear Information System (INIS)

    Workplace Safety North

    2010-01-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  7. Auxiliary mine ventilation manual

    Energy Technology Data Exchange (ETDEWEB)

    Workplace Safety North

    2010-07-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  8. Automation of an X-ray diffractometer using a manually preset control system

    International Nuclear Information System (INIS)

    Berry, T.; Prentice, P.C.

    1978-11-01

    The measurements of lattice parameters of beta silicon carbide nuclear reactor temperature monitors at Dounreay were formerly carried out using an X-ray diffractometer connected to a simple step scan control system with an analysis time of 8 hours per specimen. A system is described whereby the step scan throughout of the X-ray diffractometer is increased by using an automatic sample charger and additional control electronics, allowing round-the-clock analysis. The original system which used Harwell 2000 series electronic units has been expanded to include an AERE designed goniometer control unit, a Philips sample changer with control unit, and a Honeywell chart recorder. The integrated circuit logic used, interconnections of modules, and operating instructions are given in appendices. (UK)

  9. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Quality Assurance Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; R. Nims; K. J. Kvarfordt; C. Wharton

    2008-08-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment using a personal computer running the Microsoft Windows operating system. SAPHIRE is primarily funded by the U.S. Nuclear Regulatory Commission (NRC). The role of the INL in this project is that of software developer and tester. This development takes place using formal software development procedures and is subject to quality assurance (QA) processes. The purpose of this document is to describe how the SAPHIRE software QA is performed for Version 6 and 7, what constitutes its parts, and limitations of those processes.

  10. RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - user's manual

    International Nuclear Information System (INIS)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.; Neymotin, L.Y.

    1998-03-01

    This document is the User's Manual for the Boiling Water Reactor (BWR), and Simplified Boiling Water Reactor (SBWR) systems transient code RAMONA-4B. The code uses a three-dimensional neutron-kinetics model coupled with a multichannel, nonequilibrium, drift-flux, phase-flow model of the thermal hydraulics of the reactor vessel. The code is designed to analyze a wide spectrum of BWR core and system transients. Chapter 1 gives an overview of the code's capabilities and limitations; Chapter 2 describes the code's structure, lists major subroutines, and discusses the computer requirements. Chapter 3 is on code, auxillary codes, and instructions for running RAMONA-4B on Sun SPARC and IBM Workstations. Chapter 4 contains component descriptions and detailed card-by-card input instructions. Chapter 5 provides samples of the tabulated output for the steady-state and transient calculations and discusses the plotting procedures for the steady-state and transient calculations. Three appendices contain important user and programmer information: lists of plot variables (Appendix A) listings of input deck for sample problem (Appendix B), and a description of the plotting program PAD (Appendix C). 24 refs., 18 figs., 11 tabs

  11. CAL--ERDA users manual. [Building Design Language; LOADS, SYSTEMS, PLANT, ECONOMICS, REPORT, EXECUTIVE, CAL-ERDA

    Energy Technology Data Exchange (ETDEWEB)

    Graven, R. M.; Hirsch, P. R.

    1977-10-30

    A new set of computer programs capable of rapid and detailed analysis of energy consumption in buildings is described. The Building Design Language (BDL) has been written to allow simplified manipulation of the many variables used to describe a building and its operation. Programs presented in this manual include: (1) a Building Design Language program to analyze the input instructions, execute computer system control commands, perform data assignments and data retrieval, and control the operation of the LOADS, SYSTEMS, PLANT, ECONOMICS, and REPORT programs; (2) a LOADS analysis program which calculates peak (design) loads and hourly space loads due to ambient weather conditions and the internal occupancy, lighting, and equipment within the building, as well as variations in the size, location, orientation, construction, walls, roofs, floors, fenestrations, attachments (awnings, balconies), and shape of a building; (3) a HEATING, Ventilating, and Air-Conditioning (HVAC) SYSTEMS program capable of modeling the operation of HVAC components, including fans, coils, economizers, and humidifiers; (4) a PLANT equipment program which models the operation of boilers, chillers, electrical-generation equipment (e.g., diesel engines or turbines), heat-storage apparatus (e.g., chilled or heated water) and solar heating and/or cooling systems; (5) an ECONOMICS analysis program which calculates life-cycle costs; (6) a REPORT program which produces tables of user-selected variables and arranges them according to user-selected formats; and (7) an EXECUTIVE processor to create computer-system control commands. Libraries of weather data, typical schedule data, and data on the properties of walls, roofs, and floors are available.

  12. CAL--ERDA program manual. [Building Design Language; LOADS, SYSTEMS, PLANT, ECONOMICS, REPORT, EXECUTIVE, CAL-ERDA

    Energy Technology Data Exchange (ETDEWEB)

    Hunn, B. D.; Diamond, S. C.; Bennett, G. A.; Tucker, E. F.; Roschke, M. A.

    1977-10-01

    A set of computer programs, called Cal-ERDA, is described that is capable of rapid and detailed analysis of energy consumption in buildings. A new user-oriented input language, named the Building Design Language (BDL), has been written to allow simplified manipulation of the many variables used to describe a building and its operation. This manual provides the user with information necessary to understand in detail the Cal-ERDA set of computer programs. The new computer programs described include: an EXECUTIVE Processor to create computer system control commands; a BDL Processor to analyze input instructions, execute computer system control commands, perform assignments and data retrieval, and control the operation of the LOADS, SYSTEMS, PLANT, ECONOMICS, and REPORT programs; a LOADS analysis program that calculates peak (design) zone and hourly loads and the effect of the ambient weather conditions, the internal occupancy, lighting, and equipment within the building, as well as variations in the size, location, orientation, construction, walls, roofs, floors, fenestrations, attachments (awnings, balconies), and shape of a building; a Heating, Ventilating, and Air-Conditioning (HVAC) SYSTEMS analysis program capable of modeling the operation of HVAC components including fans, coils, economizers, humidifiers, etc.; 16 standard configurations and operated according to various temperature and humidity control schedules. A plant equipment program models the operation of boilers, chillers, electrical generation equipment (diesel or turbines), heat storage apparatus (chilled or heated water), and solar heating and/or cooling systems. An ECONOMIC analysis program calculates life-cycle costs. A REPORT program produces tables of user-selected variables and arranges them according to user-specified formats. A set of WEATHER ANALYSIS programs manipulates, summarizes and plots weather data. Libraries of weather data, schedule data, and building data were prepared.

  13. LIFE CYCLE DESIGN GUIDANCE MANUAL - ENVIRONMENTAL REQUIREMENTS AND THE PRODUCT SYSTEM

    Science.gov (United States)

    The U.S Environmental Protection Agency's (EPA) Risk Reduction Engineering Laboratory and the University of Michigan are cooperating in a project to reduce environmental impacts and health risks through product system design. The resulting framework for life cycle design is pr...

  14. User`s manual of a support system for human reliability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Yokobayashi, Masao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tamura, Kazuo

    1995-10-01

    Many kinds of human reliability analysis (HRA) methods have been developed. However, users are required to be skillful so as to use them, and also required complicated works such as drawing event tree (ET) and calculation of uncertainty bounds. Moreover, each method is not so complete that only one method of them is not enough to evaluate human reliability. Therefore, a personal computer (PC) based support system for HRA has been developed to execute HRA practically and efficiently. The system consists of two methods, namely, simple method and detailed one. The former uses ASEP that is a simplified THERP-technique, and combined method of OAT and HRA-ET/DeBDA is used for the latter. Users can select a suitable method for their purpose. Human error probability (HEP) data were collected and a database of them was built to use for the support system. This paper describes outline of the HRA methods, support functions and user`s guide of the system. (author).

  15. Users manual for the FORSS sensitivity and uncertainty analysis code system

    International Nuclear Information System (INIS)

    Lucius, J.L.; Weisbin, C.R.; Marable, J.H.; Drischler, J.D.; Wright, R.Q.; White, J.E.

    1981-01-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions and associated uncertainties. This report describes the computing environment and the modules currently used to implement FORSS Sensitivity and Uncertainty Methodology

  16. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    International Nuclear Information System (INIS)

    DALE, R.N.

    2000-01-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O and M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085

  17. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    Energy Technology Data Exchange (ETDEWEB)

    DALE, R.N.

    2000-05-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.

  18. Computer control versus manual control of systemic hypertension during cardiac surgery

    NARCIS (Netherlands)

    Hoeksel, S.A.A.P.; Blom, J.A.; Jansen, J.R.C.; Maessen, J.G.; Schreuder, J.J.

    2001-01-01

    Keywords:Cardiac surgery;hypertension;closed-loop controlBackground: We recently demonstrated the feasibility of computer controlled infusion of vasoactive drugs for the control of systemic hypertension during cardiac surgery. The objective of the current study was to investigate the effects of

  19. Users manual for the FORSS sensitivity and uncertainty analysis code system

    Energy Technology Data Exchange (ETDEWEB)

    Lucius, J.L.; Weisbin, C.R.; Marable, J.H.; Drischler, J.D.; Wright, R.Q.; White, J.E.

    1981-01-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions and associated uncertainties. This report describes the computing environment and the modules currently used to implement FORSS Sensitivity and Uncertainty Methodology.

  20. Maintenance Manual for the Automated Airdrop Information Retrieval System; Human Factors Database

    Science.gov (United States)

    1994-09-01

    Sensorimotor Abilities Loss of Cognitive/Perceptual Abilities Treatment drug therapy physical therapy cognitive therapy biofeedback therapy 63 9...Device (AOD) Oxygen System oxygen mask oxygen hose oxygen cylinders on/off valve prebreather Floatation Devices life preserver Scuba Gear Ankle Braces

  1. BIOACCUMULATION AND AQUATIC SYSTEM SIMULATOR (BASS) USER'S MANUAL BETA TEST VERSION 2.1

    Science.gov (United States)

    BASS (Bioaccumulation and Aquatic System Simulator) is a Fortran 95 simulation program that predicts the population and bioaccumulation dynamics of age-structured fish assemblages that are exposed to hydrophobic organic pollutants and class B and borderline metals that complex wi...

  2. FY 1998 Report on development project of structural residence of the next generation. Attachment 4. Frame analysis system manual; 1998 nendo jisedai kozo jutaku kaihatsu jigyo shiryohen. 4. Kako kaiseki system manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Attachment 4 of the FY 1998 report on development project of structural residence of the next generation describes the frame analysis system manual. NAPISOS is a program for analyzing static and dynamic responses of three-dimensional structures. The dynamic response is calculated by numerical integration in the time region. Dynamic load can handle dynamic exciting force, uniform seismic input and forced displacement at a node, and analyze linear elasticity and non-linear properties. The static load can handle nodal force, static seismic coefficient and forced displacement at a node, and analyze linear elasticity and non-linear properties. The static analysis also can perform analysis based on the time history response displacement method as the special case. The program implementation procedures fall into 4 general steps; first: inputting/processing of structural data, second: eigen value analysis or equivalent nodal force calculation, third: response calculation by direct integration, preparation of equivalent damping matrix or pre-stress analysis, and fourth: outputting the results. The input data related to control, structure and load are also described. (NEDO)

  3. Pdap Manual

    DEFF Research Database (Denmark)

    Pedersen, Mads Mølgaard; Larsen, Torben J.

    Pdap, Python Data Analysis Program, is a program for post processing, analysis, visualization and presentation of data e.g. simulation results and measurements. It is intended but not limited to the domain of wind turbines. It combines an intuitive graphical user interface with python scripting...... that allows automation and implementation of custom functions. This manual gives a short introduction to the graphical user interface, describes the mathematical background for some of the functions, describes the scripting API and finally a few examples on how automate analysis via scripting is presented....... The newest version, and more documentation and help on how to used, extend and automate Pdap can be found at the webpage www.hawc2.dk...

  4. Hydride heat pump. Volume I. Users manual for HYCSOS system design program. [HYCSOS code

    Energy Technology Data Exchange (ETDEWEB)

    Gorman, R.; Moritz, P.

    1978-05-01

    A method for the design and costing of a metal hydride heat pump for residential use and a computer program, HYCSOS, which automates that method are described. The system analyzed is one in which a metal hydride heat pump can provide space heating and space cooling powered by energy from solar collectors and electric power generated from solar energy. The principles and basic design of the system are presented, and the computer program is described giving detailed design and performance equations used in the program. The operation of the program is explained, and a sample run is presented. This computer program is part of an effort to design, cost, and evaluate a hydride heat pump for residential use. The computer program is written in standard Fortran IV and was run on a CDC Cyber 74 and Cyber 174 computer. A listing of the program is included as an appendix. This report is Volume 1 of a two-volume document.

  5. Thermal Insulation System Analysis Tool (TISTool) User's Manual. Version 1.0.0

    Science.gov (United States)

    Johnson, Wesley; Fesmire, James; Leucht, Kurt; Demko, Jonathan

    2010-01-01

    The Thermal Insulation System Analysis Tool (TISTool) was developed starting in 2004 by Jonathan Demko and James Fesmire. The first edition was written in Excel and Visual BasIc as macros. It included the basic shapes such as a flat plate, cylinder, dished head, and sphere. The data was from several KSC tests that were already in the public literature realm as well as data from NIST and other highly respectable sources. More recently, the tool has been updated with more test data from the Cryogenics Test Laboratory and the tank shape was added. Additionally, the tool was converted to FORTRAN 95 to allow for easier distribution of the material and tool. This document reviews the user instructions for the operation of this system.

  6. Special report writer: A flexible information management system. Documentation and user's manual

    Science.gov (United States)

    Greene, W. A.

    1976-01-01

    A special report writer (SSR) was developed which performs multiple correlations on files containing several data hierarchies. Output reports are specified in a simple notation, readily learned by persons having limited familarity with ADP. The SRR system can be adopted by other NASA installations while the basic techniques themselves are compatible with the information management needs of a wide range of organizations. Specifically, the program lends itself to generalization and can be readily adapted for other file management purposes. Extensive details on the characteristics of the SRR program are presented along with a full explanation of the system for those contemplating its application to other data bases. The complete COBOL program and documentation are available.

  7. Symbolic and Sub-Symbolic Robotic Intelligence Control System (SS-RICS) Users Manual

    Science.gov (United States)

    2017-10-01

    representations to drive intelligent systems, and the second focuses on a mathematical approach using distributed representations constructed with structures...3.1.1 Zip File • Extract the files from the zip file to a directory on your computer . • Open My Computer . • Browse to the directory where you...instructions. 3.1.2 CD • Open My Computer . • Browse to the CD-ROM drive on your computer . • Find the setup.exe file. Approved for public release

  8. The Army Communications Objectives Measurement System (ACOMS): Parental User’s Manual

    Science.gov (United States)

    1988-07-01

    system to support Army (1) assessments of advertising program effectiveness; (2) assessments of advertising strategy efficiencies; (3) management of the... advertising strategy in an integrated framework; and * (3) To support Army advertising management and planning for future strategy. 0 2 ACOMS was...recruiting goals. A second set of goals for ACOMS involved the use of ACOMS data to assess the Army’s advertising strategy . ACOMS was designed to be used

  9. Navy Activity-Level Energy Systems Planning Procedure (A-LESP) Users Manual.

    Science.gov (United States)

    1986-01-01

    temperature setpoint in OF. TON = chiller capacity in tons. Ts = average temperature of surroundings in OF. UH = unoccupied hours per week. 284...9.524) NO MAAGE OF BOILER CONTROLS $30(12)(YEARS) 1. 10 15 1 . BENEFITS /DETRIMENTS: Modern control systems can be used to optimize boiler... optimize the multiple control strategies of virtually unlimited dsi atlg ostrategies to operact with each other, complexity, and relative ease of change

  10. Modified hazard ranking system for sites with mixed radioactive and hazardous wastes. User manual

    International Nuclear Information System (INIS)

    Hawley, K.A.; Peloquin, R.A.; Stenner, R.D.

    1986-04-01

    This document describes both the original Hazard Ranking System and the modified Hazard Ranking System as they are to be used in evaluating the relative potential for uncontrolled hazardous substance facilities to cause human health or safety problems or ecological or environmental damage. Detailed instructions for using the mHRS/HRS computer code are provided, along with instructions for performing the calculations by hand. Uniform application of the ranking system will permit the DOE to identify those releases of hazardous substances that pose the greatest hazard to humans or the environment. However, the mHRS/HRS by itself cannot establish priorities for the allocation of funds for remedial action. The mHRS/HRS is a means for applying uniform technical judgment regarding the potential hazards presented by a facility relative to other facilities. It does not address the feasibility, desirability, or degree of cleanup required. Neither does it deal with the readiness or ability of a state to carry out such remedial action, as may be indicated, or to meet other conditions prescribed in CERCLA. 13 refs., 13 figs., 27 tabs

  11. Neutron dosimetry system SAIPS: Manual for users and programmers (Version 87-02)

    International Nuclear Information System (INIS)

    Berzonis, M.A.; Bondars, Kh.Ya.; Niedritis, A.M.

    1988-07-01

    SAIPS is a system used for neutron dosimetry by foil activation, containing a package of programs and a data base of neutron activation cross-sections. A description is given of the SAIPS indexed procedures and users language, which are designed for producing input data for programs unfolding neutron spectra from reaction rate measurements, for carrying out calculations and processing and comparing the results obtained, for utilizing the additional capabilities of the system, and for setting up a working version of the system from the magnetic tapes used for distribution. A description is given of the logical structure of the data sets containing the libraries of neutron cross-section and a priori spectra and also the libraries of calculated spectra. The annexes give examples of SAIPS in use, of the contents of the a priori spectra and neutron cross-section libraries, and of the contents of the SAIPS distribution tapes. SAIPS contains programs in PL/1 (opt), FORTRAN IV(H) and ASSEMBLER. 25 refs

  12. Modified hazard ranking system for sites with mixed radioactive and hazardous wastes. User manual.

    Energy Technology Data Exchange (ETDEWEB)

    Hawley, K.A.; Peloquin, R.A.; Stenner, R.D.

    1986-04-01

    This document describes both the original Hazard Ranking System and the modified Hazard Ranking System as they are to be used in evaluating the relative potential for uncontrolled hazardous substance facilities to cause human health or safety problems or ecological or environmental damage. Detailed instructions for using the mHRS/HRS computer code are provided, along with instructions for performing the calculations by hand. Uniform application of the ranking system will permit the DOE to identify those releases of hazardous substances that pose the greatest hazard to humans or the environment. However, the mHRS/HRS by itself cannot establish priorities for the allocation of funds for remedial action. The mHRS/HRS is a means for applying uniform technical judgment regarding the potential hazards presented by a facility relative to other facilities. It does not address the feasibility, desirability, or degree of cleanup required. Neither does it deal with the readiness or ability of a state to carry out such remedial action, as may be indicated, or to meet other conditions prescribed in CERCLA. 13 refs., 13 figs., 27 tabs.

  13. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1996-01-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  14. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1985-08-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  15. LOD BIM Element specification for Railway Turnout Systems Risk Mitigation using the Information Delivery Manual

    Science.gov (United States)

    Gigante-Barrera, Ángel; Dindar, Serdar; Kaewunruen, Sakdirat; Ruikar, Darshan

    2017-10-01

    Railway turnouts are complex systems designed using complex geometries and grades which makes them difficult to be managed in terms of risk prevention. This feature poses a substantial peril to rail users as it is considered a cause of derailment. In addition, derailment deals to financial losses due to operational downtimes and monetary compensations in case of death or injure. These are fundamental drivers to consider mitigating risks arising from poor risk management during design. Prevention through design (PtD) is a process that introduces tacit knowledge from industry professionals during the design process. There is evidence that Building Information Modelling (BIM) can help to mitigate risk since the inception of the project. BIM is considered an Information System (IS) were tacit knowledge can be stored and retrieved from a digital database making easy to take promptly decisions as information is ready to be analysed. BIM at the model element level entails working with 3D elements and embedded data, therefore adding a layer of complexity to the management of information along the different stages of the project and across different disciplines. In order to overcome this problem, the industry has created a framework for model progression specification named Level of Development (LOD). The paper presents an IDM based framework for design risk mitigation through code validation using the LOD. This effort resulted on risk datasets which describe graphically and non-graphically a rail turnout as the model progresses. Thus, permitting its inclusion within risk information systems. The assignment of an LOD construct to a set of data, requires specialised management and process related expertise. Furthermore, the selection of a set of LOD constructs requires a purpose based analysis. Therefore, a framework for LOD constructs implementation within the IDM for code checking is required for the industry to progress in this particular field.

  16. Structural Analysis via Generalized Interactive Graphics - STAGING. Volume IV. Appendices to System Manual.

    Science.gov (United States)

    1979-09-01

    INCLUDE READR DBO INCLUDE PWRITE DEC INCLUDE RWRITER DBO INCLUDE FCHPHAM DEC INCLUDE SETPHAM DEC INCLUDE FETSTAT DEC INCLUDE WRITE Figure B-6. System and...SY’STEM 1/3) OUTINE LENGTHS 21r L -N .-AAGE COMPASS A SN S F,3 )E JN 0A, Y N~TRk POINTS CAN 3f. ALLID df: RFAOR RWRjTE ;RWRrTER WRITE CLOSE THIS PvC)G’ A... IELT -----O ’) 8 . OL.F. . .DBDRT. IDaDAD IDBJLF ICKAGT DELPIC ENTRY CLASS: MAIN SEGMENT: (DE0) DESCI DELETE ANO DEACTIVATE ALL PICKED 2EAOS ON A LEVEL

  17. POW3D-Neutron diffusion module of the AUS system. A user's manual

    International Nuclear Information System (INIS)

    Harrington, B.V.; Pollard, J.P.; Barry, J.M.

    1996-11-01

    POW3D is a three-dimensional neutron diffusion module of the AUS modular neutronics code system. It performs eigenvalue, source of feedback-free kinetics calculations. The module includes general criticality search options and extensive editing facilities including perturbation calculations. Output options include flux or reaction rate plot files. The code permits selection from one of a variety of different solution methods (MINI, ICCG or SLOR) for inner iterations with region re balance to enhance convergence. A MINI accelerated Gauss-Siedel method is used for upscatter iterations with group rebalance to enhance a convergence. Chebyshev source extrapolation is applied for outer iterations. A detailed index is included

  18. Quality assurance of the manual OSLD Badge based personnel monitoring system

    International Nuclear Information System (INIS)

    Kumar, Munish; Gaonkar, U.P.; Koul, D.K.; Datta, D.; Singh, S.K.; Rakesh, R.B.; Kulkarni, M.S.; Ratna, P.

    2018-01-01

    Optically stimulated luminescence (OSL) based technique is widely used for monitoring of radiation workers exposed to x, gamma and beta radiations. Features such as multiple readout, short processing time, better beta response, absence of infra red signal (no heating), flexibility in the dosimeter design using binders or substrates having low melting point are associated advantages. Presently α-Al 2 O 3 :C and BeO based dosimeters are popularly used for personnel monitoring applications worldwide. The present paper describe results of the external quality control check (QAC) tests performed for the present OSLD badge based personnel monitoring system. The results were analyzed as per ANSI criteria and Trumpet curve methods

  19. A probabilistic assessment code system for derivation of clearance levels of radioactive materials. PASCLR user's manual

    International Nuclear Information System (INIS)

    Takahashi, Tomoyuki; Takeda, Seiji; Kimura, Hideo

    2001-01-01

    It is indicated that some types of radioactive material generating from the development and utilization of nuclear energy do not need to be subject regulatory control because they can only give rise to trivial radiation hazards. The process to remove such materials from regulatory control is called as 'clearance'. The corresponding levels of the concentration of radionuclides are called as 'clearance levels'. In the Nuclear Safety Commission's discussion, the deterministic approach was applied to derive the clearance levels, which are the concentrations of radionuclides in a cleared material equivalent to an individual dose criterion. Basically, realistic parameter values were selected for it. If the realistic values could not be defined, reasonably conservative values were selected. Additionally, the stochastic approaches were performed to validate the results which were obtained by the deterministic calculations. We have developed a computer code system PASCLR (Probabilistic Assessment code System for derivation of Clearance Levels of Radioactive materials) by using the Monte Carlo technique for carrying out the stochastic calculations. This report describes the structure and user information for execution of PASCLR code. (author)

  20. S/sup 3/ Financial Projection Model: preliminary user's manual and system overview

    Energy Technology Data Exchange (ETDEWEB)

    Masso, J. F.

    1976-11-30

    The S/sup 3/ Financial Projection Model is an effort undertaken to construct a pipeline economic model in order to satisfy the requirements of the US ERDA program: Energy Study of Pipeline Transportation System. A brief outline of this process is described in Appendix A, Background on the S/sup 3/ Development of a Pipeline Economic Model. A general overview of the model is presented first to indicate the rationale underlying the model and to show the linkages between the various submodels. An understanding of the basic accounting definitions and self-evident relationships between line items in the general financial accounting reports is a prerequisite for the effective application of the model. Particular attention has been paid in this system description to defining the methods of calculations utilized by the model and to describing the optional capital investment planning techniques that may be exercised with the model. The mathematical relationships underlying various planning techniques are defined and the methods for applying these techniques are discussed with illustrations and sample input data specifications. Decision tables are used to show complex decision rules applied within the model to determine the logical flow of a particular computational routine. The complete set of source data and model options are described along with the procedures for input data preparation and actual program operation.

  1. Sequence Coding and Search System for licensee event reports: coder's manual. Volume 4

    International Nuclear Information System (INIS)

    Gallaher, R.B.; Guymon, R.H.; Mays, G.T.; Poore, W.P.; Cagle, R.J.; Harrington, K.H.; Johnson, M.P.

    1985-04-01

    Operating experience data from nuclear power plants are essential for safety and reliability analyses, especially analyses of trends and patterns. The licensee event reports (LERs) that are submitted to the Nuclear Regulatory Commission (NRC) by the nuclear power plant utilities contain much of this data. The NRC's Office for Analysis and Evaluation of Operational Data (AEOD) has developed, under contract with NSIC, a system for codifying the events reported in the LERs. The primary objective of the Sequence Coding and Search System (SCSS) is to reduce the descriptive text of the LERs to coded sequences that are both computer-readable and computer-searchable. This four volume report documents and describes SCSS in detail. Volume 3 and 4 provide a technical processor, new to SCSS, the information and methodology necessary to capture descriptive data from the LER and to codify that data into a structured format and serve as reference material for the more experienced technical processor, and contains information that is essential for the more advanced user who needs to be familiar with the intricate coding techniques in order to retrieve specific details in a sequence. This volume contains updated material through amendment 1 to revision 1 of the working version of ORNL/NSIC-223, Vol. 4

  2. Sequence Coding and Search System for licensee event reports: coder's manual. Volume 3

    International Nuclear Information System (INIS)

    Gallaher, R.B.; Guymon, R.H.; Mays, G.T.; Poore, W.P.; Cagle, R.J.; Harrington, K.H.; Johnson, M.P.

    1985-04-01

    Operating experience data from nuclear power plants are essential for safety and reliability analyses, especially analyses of trends and patterns. The licensee event reports (LERs) that are submitted to the Nuclear Regulatory Commission (NRC) by the nuclear power plant utilities contain much of this data. The NRC's Office for Analysis and Evaluation of Operational Data (AEOD) has developed, under contract with NSIC, a system for codifying the events reported in the LERs. The primary objective of the Sequence Coding and Search System (SCSS) is to reduce the descriptive text of the LERs to coded sequences that are both computer-readable and computer-searchable. This four volume report documents and describes SCSS in detail. Volumes 3 and 4 provide a technical processor, new to SCSS, the information and methodology necessary to capture descriptive data from the LER and to codify that data into a structured format and serve as reference material for the more experienced technical processor, and contains information is essential for the more advanced user who needs to be familiar with the intricate coding techniques in order to retrieve specific details in a sequence. This volume contains updated material through amendment 1 to revision 1 of the working version of ORNL/NSIC-223, Vol. 3

  3. Manual for subject analysis

    International Nuclear Information System (INIS)

    2002-01-01

    This document is one in a series of publications known as the ETDE/INIS Joint Reference Series and also constitutes a part of the ETDE Procedures Manual. It presents the rules, guidelines and procedures to be adopted by centers submitting input to the International Nuclear Information System (INIS) or the Energy Technology Data Exchange (ETDE). It is a manual for the subject analysis part of input preparation, meaning the selection, subject classification, abstracting and subject indexing of relevant publications, and is to be used in conjunction with the Thesauruses, Subject Categories documents and the documents providing guidelines for the preparation of abstracts. The concept and structure of the new manual are intended to describe in a logical and efficient sequence all the steps comprising the subject analysis of documents to be reported to INIS or ETDE. The manual includes new chapters on preparatory analysis, subject classification, abstracting and subject indexing, as well as rules, guidelines, procedures, examples and a special chapter on guidelines and examples for subject analysis in particular subject fields. (g.t.; a.n.)

  4. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-IV. User's manual

    International Nuclear Information System (INIS)

    2001-01-01

    As a continuation of its efforts to provide methodologies and tools to Member States to carry out comparative assessment and analyse priority environmental issues related to the development of the electric power sector, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package WASP-IV for carrying out power generation expansion planning taking into consideration fuel availability and environmental constraints. This manual constitutes a part of this work and aims to provide users with a guide to use effectively the new version of the model WASP-IV. WASP was originally developed in 1972 by the Tennessee Valley Authority and the Oak Ridge National Laboratory in the USA to meet the IAEA needs to analyse the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or region. Previous versions of the model were used by Member States in many national and regional studies to analyse the electric power system expansion planning and the role of nuclear energy in particular. Experience gained from its application allowed development of WASP into a very comprehensive planning tool for electric power system expansion analysis. New, improved versions were developed, which took into consideration the needs expressed by the users of the programme in order to address important emerging issues being faced by the electric system planners. In 1979, WASP-IV was released and soon after became an indispensable tool in many Member States for generation expansion planning. The WASP-IV version was continually upgraded and the development of version WASP-III Plus commenced in 1992. By 1995, WASP-III Plus was completed, which followed closely the methodology of the WASP-III but incorporated new features. In order to meet the needs of electricity planners and following the recommendations of the Helsinki symposium, development of a new version of WASP was

  5. Evaluation of the PREVI® Isola automated seeder system compared to reference manual inoculation for antibiotic susceptibility testing by the disk diffusion method.

    Science.gov (United States)

    Le Page, S; van Belkum, A; Fulchiron, C; Huguet, R; Raoult, D; Rolain, J-M

    2015-09-01

    The disk diffusion (DD) method remains the most popular manual technique for antibiotic susceptibility testing (AST) in clinical microbiology laboratories. This is because of its simplicity, reproducibility, and limited cost compared to (automated) microdilution systems, which are usually less sensitive at detecting certain important mechanisms of resistance. Here, we evaluate the PREVI® Isola automated seeder system using a new protocol for spreading bacterial suspensions (eight deposits of calibrated inocula of bacteria, followed by two rounds of rotation) in comparison with manual DD reference testing on a large series of clinical and reference strains. The average time required for seeding one agar plate for DD with this new protocol was 51 s per plate, i.e., 70 agar plates/h. Reproducibility and repeatability was assessed on three reference and three randomly chosen clinical strains, as usually requested by the European Committee on Antimicrobial Susceptibility Testing (EUCAST), and was excellent compared to the manual method. The standard deviations of zones of growth inhibition showed no statistical discrimination. The correlation between the two methods, assessed using 294 clinical isolates and a panel of six antibiotics (n = 3,528 zones of growth inhibition measured), was excellent, with a correlation coefficient of 0.977. The new PREVI® Isola protocol adapted for DD had a sensitivity of 99 % and a specificity of 100 % compared to the manual technique for interpreting DD as recommended by the EUCAST.

  6. Quality assurance manual for the Department of Energy laboratory accreditation program for personnel dosimetry systems

    International Nuclear Information System (INIS)

    1987-02-01

    The overall purpose of this document is to establish a uniform approach to quality assurance. This will ensure that uniform, high-quality personnel dosimetry practices are followed by the participating testing laboratories. The document presents guidelines for calibrating and maintaining measurement and test equipment (M and TE), calibrating radiation fields, and subsequently irradiating and handling personnel dosimeters in laboratories involved in the DOE dosimetry systems testing program. Radiation energies for which the test procedures apply are photons with approximately 15 keV to 2 MeV, beta particles above 0.3 MeV, neutrons with approximately 1 keV to 2 MeV. 12 refs., 4 tabs

  7. FURNACE 2. Toroidal geometry neutronic program system method. Description and users manual

    Energy Technology Data Exchange (ETDEWEB)

    Verschuur, K.A.

    1995-10-01

    FURNACE2 is a 3-dimensional neutron/photon-transport program system for toroidal geometries. It uses ray-tracing and double-differential reflection-and transmission-coefficients and flux-kernels to calculate the angular-flux spectra inside the torus of a fusion-reactor. FURNACE2 is an extended version of FURNACE, developed for application to the neutron-diagnostics at JET, which was supported financially by JET. It is used at JET to calculate the foil-activation for the KN2 diagnostics, the angular-fluxes on the lines of sight of the KN3 profile monitors, and general background fluxes and activation of the vessel. The program is used along with MCNP, combining the advantages of each of the programs and for mutual checks. (orig.).

  8. FURNACE 2. Toroidal geometry neutronic program system method. Description and users manual

    International Nuclear Information System (INIS)

    Verschuur, K.A.

    1995-10-01

    FURNACE2 is a 3-dimensional neutron/photon-transport program system for toroidal geometries. It uses ray-tracing and double-differential reflection-and transmission-coefficients and flux-kernels to calculate the angular-flux spectra inside the torus of a fusion-reactor. FURNACE2 is an extended version of FURNACE, developed for application to the neutron-diagnostics at JET, which was supported financially by JET. It is used at JET to calculate the foil-activation for the KN2 diagnostics, the angular-fluxes on the lines of sight of the KN3 profile monitors, and general background fluxes and activation of the vessel. The program is used along with MCNP, combining the advantages of each of the programs and for mutual checks. (orig.)

  9. Transportation Routing Analysis Geographic Information System (WebTRAGIS) User's Manual

    International Nuclear Information System (INIS)

    Michelhaugh, R.D.

    2000-01-01

    In the early 1980s, Oak Ridge National Laboratory (ORNL) developed two transportation routing models: HIGHWAY, which predicts truck transportation routes, and INTERLINE, which predicts rail transportation routes. Both of these models have been used by the U.S. Department of Energy (DOE) community for a variety of routing needs over the years. One of the primary uses of the models has been to determine population-density information, which is used as input for risk assessment with the RADTRAN model, which is available on the TRANSNET computer system. During the recent years, advances in the development of geographic information systems (GISs) have resulted in increased demands from the user community for a GIS version of the ORNL routing models. In April 1994, the DOE Transportation Management Division (EM-261) held a Baseline Requirements Assessment Session with transportation routing experts and users of the HIGHWAY and INTERLINE models. As a result of the session, the development of a new GIS routing model, Transportation Routing Analysis GIS (TRAGIS), was initiated. TRAGIS is a user-friendly, GIS-based transportation and analysis computer model. The older HIGHWAY and INTERLINE models are useful to calculate routes, but they cannot display a graphic of the calculated route. Consequently, many users have experienced difficulty determining the proper node for facilities and have been confused by or have misinterpreted the text-based listing from the older routing models. Some of the primary reasons for the development of TRAGIS are (a) to improve the ease of selecting locations for routing, (b) to graphically display the calculated route, and (c) to provide for additional geographic analysis of the route

  10. The operation and maintenance manual

    International Nuclear Information System (INIS)

    Klein, W.; Krotil, H.; Stoll, A.

    1975-01-01

    The Operating Manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the Operating Manual. It contains, appropriately arranged, the necessary system and other diagrams, drawings, lists, licensing documents and similar material, which are necessary for understanding the design, for testing, for obtaining the operating licence and for the operation of individual systems and of the entire plant. (orig./RW) [de

  11. A User's Manual for MASH V1.5 - A Monte Carlo Adjoint Shielding Code System

    Energy Technology Data Exchange (ETDEWEB)

    C. O. Slater; J. M. Barnes; J. O. Johnson; J.D. Drischler

    1998-10-01

    The Monte Carlo ~djoint ~ielding Code System, MASH, calculates neutron and gamma- ray environments and radiation protection factors for armored military vehicles, structures, trenches, and other shielding configurations by coupling a forward discrete ordinates air- over-ground transport calculation with an adjoint Monte Carlo treatment of the shielding geometry. Efficiency and optimum use of computer time are emphasized. The code system includes the GRTUNCL and DORT codes for air-over-ground transport calculations, the MORSE code with the GIFT5 combinatorial geometry package for adjoint shielding calculations, and several peripheral codes that perform the required data preparations, transformations, and coupling functions. The current version, MASH v 1.5, is the successor to the original MASH v 1.0 code system initially developed at Oak Ridge National Laboratory (ORNL). The discrete ordinates calculation determines the fluence on a coupling surface surrounding the shielding geometry due to an external neutron/gamma-ray source. The Monte Carlo calculation determines the effectiveness of the fluence at that surface in causing a response in a detector within the shielding geometry, i.e., the "dose importance" of the coupling surface fluence. A coupling code folds the fluence together with the dose importance, giving the desired dose response. The coupling code can determine the dose response as a function of the shielding geometry orientation relative to the source, distance from the source, and energy response of the detector. This user's manual includes a short description of each code, the input required to execute the code along with some helpful input data notes, and a representative sample problem.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-04-01

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

  13. Caltrans : construction manual

    Science.gov (United States)

    2009-08-01

    Caltrans intends this manual as a resource for all personnel engaged in contract administration. The manual establishes policies and procedures for the construction phase of Caltrans projects. However, this manual is not a contract document. It impos...

  14. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Code Reference Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; K. J. Kvarfordt; S. T. Wood

    2008-08-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment (PRA) using a personal computer. SAPHIRE is funded by the U.S. Nuclear Regulatory Commission (NRC) and developed by the Idaho National Laboratory (INL). The INL's primary role in this project is that of software developer. However, the INL also plays an important role in technology transfer by interfacing and supporting SAPHIRE users comprised of a wide range of PRA practitioners from the NRC, national laboratories, the private sector, and foreign countries. SAPHIRE can be used to model a complex system’s response to initiating events, quantify associated damage outcome frequencies, and identify important contributors to this damage (Level 1 PRA) and to analyze containment performance during a severe accident and quantify radioactive releases (Level 2 PRA). It can be used for a PRA evaluating a variety of operating conditions, for example, for a nuclear reactor at full power, low power, or at shutdown conditions. Furthermore, SAPHIRE can be used to analyze both internal and external initiating events and has special features for transforming models built for internal event analysis to models for external event analysis. It can also be used in a limited manner to quantify risk in terms of release consequences to both the public and the environment (Level 3 PRA). SAPHIRE includes a separate module called the Graphical Evaluation Module (GEM). GEM provides a highly specialized user interface with SAPHIRE that automates SAPHIRE process steps for evaluating operational events at commercial nuclear power plants. Using GEM, an analyst can estimate the risk associated with operational events in a very efficient and expeditious manner. This reference guide will introduce the SAPHIRE Version 7.0 software. A brief discussion of the purpose and history of the software is included along with

  15. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Code Reference Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; K. J. Kvarfordt; S. T. Wood

    2006-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment (PRA) using a personal computer. SAPHIRE is funded by the U.S. Nuclear Regulatory Commission (NRC) and developed by the Idaho National Laboratory (INL). The INL's primary role in this project is that of software developer. However, the INL also plays an important role in technology transfer by interfacing and supporting SAPHIRE users comprised of a wide range of PRA practitioners from the NRC, national laboratories, the private sector, and foreign countries. SAPHIRE can be used to model a complex system’s response to initiating events, quantify associated damage outcome frequencies, and identify important contributors to this damage (Level 1 PRA) and to analyze containment performance during a severe accident and quantify radioactive releases (Level 2 PRA). It can be used for a PRA evaluating a variety of operating conditions, for example, for a nuclear reactor at full power, low power, or at shutdown conditions. Furthermore, SAPHIRE can be used to analyze both internal and external initiating events and has special features for ansforming models built for internal event analysis to models for external event analysis. It can also be used in a limited manner to quantify risk in terms of release consequences to both the public and the environment (Level 3 PRA). SAPHIRE includes a separate module called the Graphical Evaluation Module (GEM). GEM provides a highly specialized user interface with SAPHIRE that automates SAPHIRE process steps for evaluating operational events at commercial nuclear power plants. Using GEM, an analyst can estimate the risk associated with operational events in a very efficient and expeditious manner. This reference guide will introduce the SAPHIRE Version 7.0 software. A brief discussion of the purpose and history of the software is included along with

  16. Functional classifications for cerebral palsy: correlations between the gross motor function classification system (GMFCS), the manual ability classification system (MACS) and the communication function classification system (CFCS).

    Science.gov (United States)

    Compagnone, Eliana; Maniglio, Jlenia; Camposeo, Serena; Vespino, Teresa; Losito, Luciana; De Rinaldis, Marta; Gennaro, Leonarda; Trabacca, Antonio

    2014-11-01

    This study aimed to investigate a possible correlation between the gross motor function classification system-expanded and revised (GMFCS-E&R), the manual abilities classification system (MACS) and the communication function classification system (CFCS) functional levels in children with cerebral palsy (CP) by CP subtype. It was also geared to verify whether there is a correlation between these classification systems and intellectual functioning (IF) and parental socio-economic status (SES). A total of 87 children (47 males and 40 females, age range 4-18 years, mean age 8.9±4.2) were included in the study. A strong correlation was found between the three classifications: Level V of the GMFCS-E&R corresponds to Level V of the MACS (rs=0.67, p=0.001); the same relationship was found for the CFCS and the MACS (rs=0.73, p<0.001) and for the GMFCS-E&R and the CFCS (rs=0.61, p=0.001). The correlations between the IQ and the global functional disability profile were strong or moderate (GMFCS and IQ: rs=0.66, p=0.001; MACS and IQ: rs=0.58, p=0.001; CFCS and MACS: rs=0.65, p=0.001). The Kruskal-Wallis test was used to determine if there were differences between the GMFCS-E&R, the CFCS and the MACS by CP type. CP types showed different scores for the IQ level (Chi-square=8.59, df=2, p=0.014), the GMFCS-E&R (Chi-square=36.46, df=2, p<0.001), the CFCS (Chi-square=12.87, df=2, p=0.002), and the MACS Level (Chi-square=13.96, df=2, p<0.001) but no significant differences emerged for the SES (Chi-square=1.19, df=2, p=0.554). This study shows how the three functional classifications (GMFCS-E&R, CFCS and MACS) complement each other to provide a better description of the functional profile of CP. The systematic evaluation of the IQ can provide useful information about a possible future outcome for every functional level. The SES does not appear to affect functional profiles. Copyright © 2014 Elsevier Ltd. All rights reserved.

  17. EXFOR systems manual

    International Nuclear Information System (INIS)

    McLane, Victoria

    2000-01-01

    EXFOR is the exchange format for the transmission of experimental nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. This report contains the agreed coding rules and format. The present version is identical to the report BNL-NCS-63330 (April 2000) except for very few minor corrections introduced by IAEA-NDS. (author)

  18. Investigation of Advanced Counterrotation Blade Configuration Concepts for High Speed Turboprop Systems. Task 8: Cooling Flow/heat Transfer Analysis User's Manual

    Science.gov (United States)

    Hall, Edward J.; Topp, David A.; Heidegger, Nathan J.; Delaney, Robert A.

    1994-01-01

    The focus of this task was to validate the ADPAC code for heat transfer calculations. To accomplish this goal, the ADPAC code was modified to allow for a Cartesian coordinate system capability and to add boundary conditions to handle spanwise periodicity and transpiration boundaries. This user's manual describes how to use the ADPAC code as developed in Task 5, NAS3-25270, including the modifications made to date in Tasks 7 and 8, NAS3-25270.

  19. Safety and feasibility of atrial fibrillation ablation using Amigo® system versus manual approach: A pilot study

    Directory of Open Access Journals (Sweden)

    Antonio Scarà

    2018-03-01

    Full Text Available Background: The Amigo® Remote Catheter System is a relatively new robotic system for catheter navigation. This study compared feasibility and safety using Amigo (RCM versus manual catheter manipulation (MCM to treat paroxysmal atrial fibrillation (PAF. Contact force (CF and force-time integral (FTI values obtained during pulmonary vein isolation (PVI ablation were compared. Methods: Forty patients were randomly selected for either RCM (20 or MCM (20. All were studied with the Thermocool® SmartTouch® force-sensing catheter (STc. Contact Force (CF, Force Time Integral (FTI and procedure-related data, were measured/stored in the CARTO®3. Results: All cases achieved complete PVI without major complications. Mean CF was significantly higher in the RCM group (13.3 ± 7.7 g in RCM vs. 12.04 ± 7.42 g in MCM p < 0.001, as was overall mean FTI (425.6 gs ± 199.6 gs with RCM and 407.5 gs ± 288.0 gs in MCM (p = 0.007 and was more likely to fall into the optimal FTI range (400-1000 using RCM (66.1% versus 49.1%, p < 0.001. FTI was significantly more likely to fall within the optimal range in each PV, as was CF within its optimal range in the right PVs, but trended higher in the left PVs. Freedom from atrial tachyarrhythmia was 90.0% for the RCM and 70.0% for the MCM group (p = 0,12 at 540 days follow-up. Conclusions: This pilot study suggests that use of the Amigo RCM system, with STc catheter, seems to be safe and effective for PVI ablation in paroxysmal AF patients. A not statistically significant favorable trend was observed for RCM in term of AF-free survival. Keywords: Atrial fibrillation, Catheter ablation, Remote robotic ablation

  20. A survey of dairy calf management practices among farms using manual and automated milk feeding systems in Canada.

    Science.gov (United States)

    Medrano-Galarza, Catalina; LeBlanc, Stephen J; DeVries, Trevor J; Jones-Bitton, Andria; Rushen, Jeffrey; Marie de Passillé, Anne; Haley, Derek B

    2017-08-01

    Dairy calves in North America traditionally are housed individually and fed by manual milk feeding (MMF) systems with buckets or bottles. Automated milk feeders (AMF) allow for more natural milk feeding frequencies and volumes, and calves are usually housed in groups. The objectives of this study were to (1) determine the prevalence of various milk-fed calf management and feeding practices and (2) compare these practices between dairy farms using MMF and AMF systems. A national online survey was performed from January to May 2015 to quantify management practices for the care of milk-fed dairy calves in Canada. A total of 670 responses were received (6% of all dairy farms in Canada). Among respondents, 16% used AMF and 84% used MMF. Seventy percent of the farms using AMF had freestall barns compared with only 48% of those using MMF. A greater proportion of AMF farms (30%) also had automatic milking systems (AMS) compared with MMF farms (8%). Among tiestall farms, a herd size of >80 milking cows was associated with having an AMF [odds ratio (OR) = 3.8; 95% confidence interval (CI): 1.6-11.4]. For freestall or bedded-pack farms, a herd size of >80 milking cows (OR = 3.5; CI: 1.8-6.6), having an AMS (OR = 3.1; CI: 1.6-5.7), and use of cow brushes (OR = 3.1; CI: 1.3-6.9) were associated with having an AMF. Calves fed with AMS typically were housed in groups of 10 to 15, whereas almost 76% of the farms with MMF housed calves individually. Although both AMF and MMF farms fed similar amounts of milk in the first week of life (median = 6 L/d), the cumulative volume fed in the first 4 wk differed significantly, with a median of 231 versus 182 L for AMF and MMF, respectively. Median peak milk allowance was higher for AMF than for MMF (10 vs. 8 L/d, respectively). In summary, farms using AMF were larger, provided more milk to calves, and used more automation in general (i.e., in other areas of their operation). These data provide insights into calf-rearing practices across

  1. Mechanical reduction of the intracanal Enterococcus faecalis population by Hyflex CM, K3XF, ProTaper Next, and two manual instrument systems: an in vitro comparative study.

    Science.gov (United States)

    Tewari, Rajendra K; Ali, Sajid; Mishra, Surendra K; Kumar, Ashok; Andrabi, Syed Mukhtar-Un-Nisar; Zoya, Asma; Alam, Sharique

    2016-05-01

    In the present study, the effectiveness of three rotary and two manual nickel titanium instrument systems on mechanical reduction of the intracanal Enterococcus faecalis population was evaluated. Mandibular premolars with straight roots were selected. Teeth were decoronated and instrumented until 20 K file and irrigated with physiological saline. After sterilization by ethylene oxide gas, root canals were inoculated with Enterococcus faecalis. The specimens were randomly divided into five groups for canal instrumentation: Manual Nitiflex and Hero Shaper nickel titanium files, and rotary Hyflex CM, ProTaper Next, and K3XF nickel titanium files. Intracanal bacterial sampling was done before and after instrumentation. After serial dilution, samples were plated onto the Mitis Salivarius agar. The c.f.u. grown were counted, and log10 transformation was calculated. All instrumentation systems significantly reduced the intracanal bacterial population after root canal preparation. ProTaper Next was found to be significantly more effective than Hyflex CM and manual Nitiflex and Hero Shaper. However, ProTaper Next showed no significant difference with K3XF. Canal instrumentation by all the file systems significantly reduced the intracanal Enterococcus faecalis counts. ProTaper Next was found to be most effective in reducing the number of bacteria than other rotary or hand instruments. © 2014 Wiley Publishing Asia Pty Ltd.

  2. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD`s Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases & Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  3. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD's Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  4. Irrigation Training Manual. Planning, Design, Operation, and Management of Small-Scale Irrigation Systems [and] Irrigation Reference Manual. A Technical Reference to Be Used with the Peace Corps Irrigation Training Manual T0076 in the Selection, Planning, Design, Operation, and Management of Small-Scale Irrigation Systems.

    Science.gov (United States)

    Salazar, LeRoy; And Others

    This resource for trainers involved in irrigated agriculture training for Peace Corps volunteers consists of two parts: irrigation training manual and irrigation reference manual. The complete course should fully prepare volunteers serving as irrigation, specialists to plan, implement, evaluate and manage small-scale irrigation projects in arid,…

  5. Forging Alliances with Protection and Advocacy Systems: A Training Manual for Parents of Children with Emotional Disorders.

    Science.gov (United States)

    Petr, Christopher G.

    This manual is intended to be used in conjunction with a 1-day training workshop to help parents of children with emotional disorders establish working alliances with protection and advocacy agencies for people with mental illness (PAMIs). The workshop prepares parents for developing specific plans for forging alliances with the state PAMI. The…

  6. Integrated Information Support System (IISS). Volume 8. User Interface Subsystem. Part 39. Electronic Documentation System (EDS) User’s Manual

    Science.gov (United States)

    1990-09-30

    conveying any rights or permission to manufacture, use, or market any patented invention that may in any way be related thereto. This technical report...24 Layout Editor A:’on D"D Nline luo ert Profile Description ED,7 tntrDSLEI * PM5SLE a, )catioq Figure 5-8 Edit Document Profile The system will now

  7. ETAP user's manual

    International Nuclear Information System (INIS)

    Watanabe, Norio; Higuchi, Suminori.

    1990-11-01

    The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

  8. OASIS User Manual

    CERN Document Server

    Bojtar, L

    2009-01-01

    The OASIS system has been operational for years now. After a long development the project has reached a state where the number of features it provides exceeds largely what most of its users knows about. The author felt it was time to write a user manual explaining all the functionality of the viewer application. This document is a user manual, concentrating on the functionality of the viewer from the user’s point of view. There are already documents available on the project’s web site about the technical aspects at http://project-oasis.web.cern.ch/project-oasis/presentations.htm . There was an attempt to produce a tutorial on the viewer, but it didn’t get much further than the table of contents, that however is well thought. The structure of this user manual follows the same principle, the basic and most often used features are grouped together. Advanced or less often used features are described in a separate chapter. There is a second organizational principle, features belong to different levels: chann...

  9. SYVAC3 manual

    International Nuclear Information System (INIS)

    Andres, T.H.

    2000-01-01

    SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

  10. SYVAC3 manual

    Energy Technology Data Exchange (ETDEWEB)

    Andres, T.H

    2000-07-01

    SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

  11. ELCOS: the PSI code system for LWR core analysis. Part II: user`s manual for the fuel assembly code BOXER

    Energy Technology Data Exchange (ETDEWEB)

    Paratte, J.M.; Grimm, P.; Hollard, J.M. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-02-01

    ELCOS is a flexible code system for the stationary simulation of light water reactor cores. It consists of the four computer codes ETOBOX, BOXER, CORCOD and SILWER. The user`s manual of the second one is presented here. BOXER calculates the neutronics in cartesian geometry. The code can roughly be divided into four stages: - organisation: choice of the modules, file manipulations, reading and checking of input data, - fine group fluxes and condensation: one-dimensional calculation of fluxes and computation of the group constants of homogeneous materials and cells, - two-dimensional calculations: geometrically detailed simulation of the configuration in few energy groups, - burnup: evolution of the nuclide densities as a function of time. This manual shows all input commands which can be used while running the different modules of BOXER. (author) figs., tabs., refs.

  12. Manual versus Automated Rodent Behavioral Assessment: Comparing Efficacy and Ease of Bederson and Garcia Neurological Deficit Scores to an Open Field Video-Tracking System.

    Science.gov (United States)

    Desland, Fiona A; Afzal, Aqeela; Warraich, Zuha; Mocco, J

    2014-01-01

    Animal models of stroke have been crucial in advancing our understanding of the pathophysiology of cerebral ischemia. Currently, the standards for determining neurological deficit in rodents are the Bederson and Garcia scales, manual assessments scoring animals based on parameters ranked on a narrow scale of severity. Automated open field analysis of a live-video tracking system that analyzes animal behavior may provide a more sensitive test. Results obtained from the manual Bederson and Garcia scales did not show significant differences between pre- and post-stroke animals in a small cohort. When using the same cohort, however, post-stroke data obtained from automated open field analysis showed significant differences in several parameters. Furthermore, large cohort analysis also demonstrated increased sensitivity with automated open field analysis versus the Bederson and Garcia scales. These early data indicate use of automated open field analysis software may provide a more sensitive assessment when compared to traditional Bederson and Garcia scales.

  13. MORT User's Manual for use with the Management Oversight and Risk Tree analytical logic diagram. [Contains a list of System Safety Development Center publications

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.W.; Eicher, R.W.

    1992-02-01

    This report contains the User's Manual for MORT (Management Oversight and Risk Tree), a logic diagram in the form of a work sheet'' that illustrates a long series of interrelated questions. MORT is a comprehensive analytical procedure that provides a disciplined method for determining the causes and contributing factors of major accidents. Alternatively, it serves as a tool to evaluate the quality of an existing system. While similar in many respects to fault tree analysis, MORT is more generalized and presents over 1,500 specific elements of an ideal universal'' management program for optimizing environment, safety and health, and other programs. This User's Manual is intended to be used with the MORT diagram dated February 1992.

  14. Manual versus Automated Rodent Behavioral Assessment: Comparing Efficacy and Ease of Bederson and Garcia Neurological Deficit Scores to an Open Field Video-Tracking System

    Directory of Open Access Journals (Sweden)

    Fiona A. Desland

    2014-01-01

    Full Text Available Animal models of stroke have been crucial in advancing our understanding of the pathophysiology of cerebral ischemia. Currently, the standards for determining neurological deficit in rodents are the Bederson and Garcia scales, manual assessments scoring animals based on parameters ranked on a narrow scale of severity. Automated open field analysis of a live-video tracking system that analyzes animal behavior may provide a more sensitive test. Results obtained from the manual Bederson and Garcia scales did not show significant differences between pre- and post-stroke animals in a small cohort. When using the same cohort, however, post-stroke data obtained from automated open field analysis showed significant differences in several parameters. Furthermore, large cohort analysis also demonstrated increased sensitivity with automated open field analysis versus the Bederson and Garcia scales. These early data indicate use of automated open field analysis software may provide a more sensitive assessment when compared to traditional Bederson and Garcia scales.

  15. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0: Integrated Reliability and Risk Analysis System (IRRAS) reference manual. Volume 2

    International Nuclear Information System (INIS)

    Russell, K.D.; Kvarfordt, K.J.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the use the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification to report generation. Version 1.0 of the IRRAS program was released in February of 1987. Since then, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 5.0 and is the subject of this Reference Manual. Version 5.0 of IRRAS provides the same capabilities as earlier versions and ads the ability to perform location transformations, seismic analysis, and provides enhancements to the user interface as well as improved algorithm performance. Additionally, version 5.0 contains new alphanumeric fault tree and event used for event tree rules, recovery rules, and end state partitioning

  16. Culture expansion of adipose derived stromal cells. A closed automated Quantum Cell Expansion System compared with manual flask-based culture

    DEFF Research Database (Denmark)

    Haack-Sørensen, Mandana; Follin, Bjarke; Juhl, Morten

    2016-01-01

    ) over two passages in the automated and functionally closed Quantum Cell Expansion System (Quantum system) is compared with traditional manual cultivation. Methods: Stromal vascular fraction was isolated from abdominal fat, suspended in α-MEM supplemented with 10% Fetal Bovine Serum and seeded...... into either T75 flasks or a Quantum system that had been coated with cryoprecipitate. The cultivation of ASCs from SVF was performed in 3 ways: flask to flask; flask to Quantum system; and Quantum system to Quantum system. In all cases, quality controls were conducted for sterility, mycoplasmas......, and endotoxins, in addition to the assessment of cell counts, viability, immunophenotype, and differentiation potential. Results: The viability of ASCs passage 0 (P0) and P1 was above 96%, regardless of cultivation in flasks or Quantum system. Expression of surface markers and differentiation potential...

  17. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    Energy Technology Data Exchange (ETDEWEB)

    Kumada, Hiroaki; Torii, Yoshiya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-09-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

  18. Environmental Compliance Guide. Guidance manual for Department of Energy compliance with the Clean Water Act: National Pollutant Discharge Elimination System (NPDES)

    Energy Technology Data Exchange (ETDEWEB)

    1982-07-01

    This manual provides general guidance for Department of Energy (DOE) officials for complying with Sect. 402 of the Clean Water Act (CWA) of 1977 and amendments. Section 402 authorizes the US Environmental Protection Agency (EPA) or states with EPA approved programs to issue National Pollutant Discharge Elimination System (NPDES) permits for the direct discharge of waste from a point source into waters of the United States. Although the nature of a project dictates the exact information requirements, every project has similar information requirements on the environmental setting, type of discharge(s), characterization of effluent, and description of operations and wastewater treatment. Additional information requirements for projects with ocean discharges, thermal discharges, and cooling water intakes are discussed. Guidance is provided in this manual on general methods for collecting, analyzing, and presenting information for an NPDES permit application. The NPDES program interacts with many sections of the CWA; therefore, background material on pertinent areas such as effluent limitations, water quality standards, toxic substances, and nonpoint source pollutants is included in this manual. Modifications, variances, and extensions applicable to NPDES permits are also discussed.

  19. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    CERN Document Server

    Kumada, H

    2002-01-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to ...

  20. Surveyor Manual

    DEFF Research Database (Denmark)

    Blyt, Henrik; Hessellund, Regner Bæk

    The project proposes a new training system aiming at the creation of a new profession, the building surveyor, working for the preservation of the existing built stock and extension of its lifetime, by means of regular, expert observation, operation and maintenance. The results of this activity...... in the field, at local and national level. The training system will operate at two different levels, a) for higher-education graduates, mainly architects and engineers, at postgraduate level, providing a new qualification as ‘building surveyor’ and b) for graduates of secondary schools, post-secondary training...... providing the qualification of ‘building maintenance technician’. Being addressed to people seeking jobs, but also to professionals already working in domains connected to the administration and maintenance of building stock, such as local administration, public and private companies owning buildings, SMEs...

  1. Optoelectronics circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Optoelectronics Circuits Manual covers the basic principles and characteristics of the best known types of optoelectronic devices, as well as the practical applications of many of these optoelectronic devices. The book describes LED display circuits and LED dot- and bar-graph circuits and discusses the applications of seven-segment displays, light-sensitive devices, optocouplers, and a variety of brightness control techniques. The text also tackles infrared light-beam alarms and multichannel remote control systems. The book provides practical user information and circuitry and illustrations.

  2. Rural Gas Program manual

    Energy Technology Data Exchange (ETDEWEB)

    1987-11-01

    The intent and purpose of this manual is to describe the various guideliness and administrative procedures associated with the Alberta Rural Gas Program and to consolidate and expand upon the legislation under which the Program has been developed. It is intended primarily for the use and information of rural gas distributors, their agents, and other private or government parties having an interest in the Rural Gas Program. Information is presented on: rural gas franchises, technical applications, contracts and tenders, determination of system capital costs for grant support, grants, Gas Alberta brokerage arrangements, insurance coverage, utility rights-of-way, and lien notes.

  3. FISPACT 97: user manual

    International Nuclear Information System (INIS)

    Forrest, R.A.; Sublet, J.-Ch.

    1997-05-01

    FISPACT is the inventory code included in the European Activation System (EASY). A new version of FISPACT: FISPACT-97 has been developed and this report is the User manual for the code. It explains the use of all the code words used in the input file to specify a FISPACT run and describes how all the data files are connected. A series of appendices cover the working of the code and the physical and mathematical details. Background information on the data files and extensive examples of input files suitable for various applications are included. (Author)

  4. Methane measurements manual; Handbok metanmaetningar

    Energy Technology Data Exchange (ETDEWEB)

    Holmgren, Magnus Andreas (SP Technical research institute of Sweden, Boraas (Sweden))

    2011-02-15

    Emissions to air in different parts of the system may arise in biogas plants, where there is biological treatment of organic matter by anaerobic degradation, and during upgrading of biogas to vehicle fuel. There are mainly four reasons why these emissions must be minimized. These are safety, greenhouse gas emissions, economy and smell. This manual gathers experience of several years of work with measurement of methane emissions from biogas and upgrading facilities. This work has been done mainly in the context of Swedish Waste Management's system of voluntary commitment. The purpose of this manual is to standardize methods and procedures when methane measurements are carried out so that the results are comparable between different providers. The main target group of the manual is measurement consultants performing such measurements. Calculation template in Excel is part of the manual, which further contributes to the measurements evaluated in a standardized way. The manual contains several examples which have been calculated in the accompanying Excel template. The handbook also contains a chapter mainly intended for facility staff, in which implementation of accurate leak detection is described, and where there are hints of a system of so-called intermediate inspections to detect leaks in time

  5. INIS: Database manual

    International Nuclear Information System (INIS)

    2003-01-01

    This document is one in a series of publications known as the INIS Reference Series. It is intended for users of INIS (International Nuclear Information System) output data on various media (FTP file, CD-ROM, e-mail file, earlier magnetic tape, cartridge, etc.). This manual provides a description of each data element including information on contents, structure and usage as well as historical overview of additions, deletions and changes of data elements and their contents that have taken place over the years. Each record contains certain control data fields (001-009), one, two or three bibliographic levels, a set of descriptors, and zero, one or more abstracts, one in English and optionally one or more in another language. In order to facilitate the description of the system, the sequence of data elements is based on the input or, as it is internally called, worksheet format which differs from the exchange format described in the manual IAEA-INIS-7. A separate section is devoted to each data element and deviations from the exchange format are indicated whenever present. As the Record Leader and the Directory are sufficiently explained in Chapter 3.1 of IAEA-INIS-7, the contents of this manual are limited to control fields and data fields; the detailed explanations are intended to supplement the basic information given in Chapter 3.2 of IAEA-INIS-7. Bibliographic levels are used to identify component parts of a publication, i.e. chapters in a book, articles in a journal issue, conference papers in a proceedings volume. All bibliographic levels contained in a record are given in a control data field. Each bibliographic level identifier appears in the subdirectory with a pointer to its position in the record

  6. ARIES NDA Robot operators' manual

    International Nuclear Information System (INIS)

    Scheer, N.L.; Nelson, D.C.

    1998-05-01

    The ARIES NDA Robot is an automation device for servicing the material movements for a suite of Non-destructive assay (NDA) instruments. This suite of instruments includes a calorimeter, a gamma isotopic system, a segmented gamma scanner (SGS), and a neutron coincidence counter (NCC). Objects moved by the robot include sample cans, standard cans, and instrument plugs. The robot computer has an RS-232 connection with the NDA Host computer, which coordinates robot movements and instrument measurements. The instruments are expected to perform measurements under the direction of the Host without operator intervention. This user's manual describes system startup, using the main menu, manual operation, and error recovery

  7. Ziptrack manual

    International Nuclear Information System (INIS)

    Ito, A.; Bosworth, W.; Rutherford, J.; Lynch, A.; Tung, L.; Yang, W.

    1983-07-01

    A phenolic cart holding 3 mutually perpendicular search coils is moved through an luminum beam into the magnetic field. Coil voltages re integrated and digitized through a Data Translation 1712 ADC. The cart is controlled and the data is processed by an on-line PDP-11/05 computer. The results are displayed on a Tektronix 4010 terminal, stored on 9 track, 800 bpi tapes, and optionally recorded on a hard copy. Software on a floppy disk controls the system. The position of the cart is located by an encoder and is checked along the beam line by optical switches. One encoder count equals 0.01945 in.. The X and Y positions are changed by manipulators at each end of the beam. 625 horizontal or 500 vertical counts equal 1 in.. The desired field mapping can be automatically set up by programming a grid of encoder counts on the ''SHOW STATUS'' chart. A ziptrack command summary is given. Following that is a typical procedure for ziptrack operations. Also attached are time constants for the integrators and coil calibrations for 30 ft. and 100 ft. long cables

  8. Multi-modal assessment of on-road demand of voice and manual phone calling and voice navigation entry across two embedded vehicle systems

    Science.gov (United States)

    Mehler, Bruce; Kidd, David; Reimer, Bryan; Reagan, Ian; Dobres, Jonathan; McCartt, Anne

    2016-01-01

    Abstract One purpose of integrating voice interfaces into embedded vehicle systems is to reduce drivers’ visual and manual distractions with ‘infotainment’ technologies. However, there is scant research on actual benefits in production vehicles or how different interface designs affect attentional demands. Driving performance, visual engagement, and indices of workload (heart rate, skin conductance, subjective ratings) were assessed in 80 drivers randomly assigned to drive a 2013 Chevrolet Equinox or Volvo XC60. The Chevrolet MyLink system allowed completing tasks with one voice command, while the Volvo Sensus required multiple commands to navigate the menu structure. When calling a phone contact, both voice systems reduced visual demand relative to the visual–manual interfaces, with reductions for drivers in the Equinox being greater. The Equinox ‘one-shot’ voice command showed advantages during contact calling but had significantly higher error rates than Sensus during destination address entry. For both secondary tasks, neither voice interface entirely eliminated visual demand. Practitioner Summary: The findings reinforce the observation that most, if not all, automotive auditory–vocal interfaces are multi-modal interfaces in which the full range of potential demands (auditory, vocal, visual, manipulative, cognitive, tactile, etc.) need to be considered in developing optimal implementations and evaluating drivers’ interaction with the systems. Social Media: In-vehicle voice-interfaces can reduce visual demand but do not eliminate it and all types of demand need to be taken into account in a comprehensive evaluation. PMID:26269281

  9. Multi-modal assessment of on-road demand of voice and manual phone calling and voice navigation entry across two embedded vehicle systems.

    Science.gov (United States)

    Mehler, Bruce; Kidd, David; Reimer, Bryan; Reagan, Ian; Dobres, Jonathan; McCartt, Anne

    2016-03-01

    One purpose of integrating voice interfaces into embedded vehicle systems is to reduce drivers' visual and manual distractions with 'infotainment' technologies. However, there is scant research on actual benefits in production vehicles or how different interface designs affect attentional demands. Driving performance, visual engagement, and indices of workload (heart rate, skin conductance, subjective ratings) were assessed in 80 drivers randomly assigned to drive a 2013 Chevrolet Equinox or Volvo XC60. The Chevrolet MyLink system allowed completing tasks with one voice command, while the Volvo Sensus required multiple commands to navigate the menu structure. When calling a phone contact, both voice systems reduced visual demand relative to the visual-manual interfaces, with reductions for drivers in the Equinox being greater. The Equinox 'one-shot' voice command showed advantages during contact calling but had significantly higher error rates than Sensus during destination address entry. For both secondary tasks, neither voice interface entirely eliminated visual demand. Practitioner Summary: The findings reinforce the observation that most, if not all, automotive auditory-vocal interfaces are multi-modal interfaces in which the full range of potential demands (auditory, vocal, visual, manipulative, cognitive, tactile, etc.) need to be considered in developing optimal implementations and evaluating drivers' interaction with the systems. Social Media: In-vehicle voice-interfaces can reduce visual demand but do not eliminate it and all types of demand need to be taken into account in a comprehensive evaluation.

  10. A Manual of Style.

    Science.gov (United States)

    Nebraska State Dept. of Education, Lincoln.

    This "Manual of Style" is offered as a guide to assist Nebraska State employees in producing quality written communications and in presenting a consistently professional image of government documents. The manual is not designed to be all-inclusive. Sections of the manual discuss formatting documents, memorandums, letters, mailing…

  11. WAM-E user's manual

    International Nuclear Information System (INIS)

    Rayes, L.G.; Riley, J.E.

    1986-07-01

    The WAM-E series of mainframe computer codes have been developed to efficiently analyze the large binary models (e.g., fault trees) used to represent the logic relationships within and between the systems of a nuclear power plant or other large, multisystem entity. These codes have found wide application in reliability and safety studies of nuclear power plant systems. There are now nine codes in the WAM-E series, with six (WAMBAM/WAMTAP, WAMCUT, WAMCUT-II, WAMFM, WAMMRG, and SPASM) classified as Type A Production codes and the other three (WAMFTP, WAMTOP, and WAMCONV) classified as Research codes. This document serves as a combined User's Guide, Programmer's Manual, and Theory Reference for the codes, with emphasis on the Production codes. To that end, the manual is divided into four parts: Part I, Introduction; Part II, Theory and Numerics; Part III, WAM-E User's Guide; and Part IV, WAMMRG Programmer's Manual

  12. WISDAAM software programmer's manual

    International Nuclear Information System (INIS)

    Ball, J.R.

    1992-10-01

    The WISDAAM system was developed to provide quality control over test data associated with in situ testing at the Waste Isolation Pilot Plant (WIPP). Assurance of data quality is of critical importance as these tests supply the information which will be used for development and verification of the technology required for repository implementation. The amount of data collected from the tests, which are some of the largest ever fielded in an underground facility, prompted the undertaking of a major project task to address data processing. The goal was to create a conceptual umbrella under which all of the activities associated with processing WIPP data (i.e., data reduction, archiving, retrieval, etc.) could be grouped. The WISDAAM system was the product of this task. The overall system covers electronic as well as manual data processing; however, this document deals primarily with those operations implemented by software running on a VAX computer

  13. LCS Users Manual

    International Nuclear Information System (INIS)

    Redd, A.J.; Ignat, D.W.

    1998-01-01

    The Lower Hybrid Simulation Code (LSC) is a computational model of lower hybrid current drive in the presence of an electric field. Details of geometry, plasma profiles, and circuit equations are treated. Two-dimensional velocity space effects are approximated in a one-dimensional Fokker-Planck treatment. The LSC was originally written to be a module for lower hybrid current drive called by the Tokamak Simulation Code (TSC), which is a numerical model of an axisymmetric tokamak plasma and the associated control systems. The TSC simulates the time evolution of a free boundary plasma by solving the MHD equations on a rectangular computational grid. The MHD equations are coupled to the external circuits (representing poloidal field coils) through the boundary conditions. The code includes provisions for modeling the control system, external heating, and fusion heating. The LSC module can also be called by the TRANSP code. TRANSP represents the plasma with an axisymmetric, fixed-boundary model and focuses on calculation of plasma transport to determine transport coefficients from data on power inputs and parameters reached. This manual covers the basic material needed to use the LSC. If run in conjunction with TSC, the ''TSC Users Manual'' should be consulted. If run in conjunction with TRANSP, on-line documentation will be helpful. A theoretical background of the governing equations and numerical methods is given. Information on obtaining, compiling, and running the code is also provided

  14. DESIGN OF MANUAL MATERIAL HANDLING SYSTEM THROUGH COMPUTER AIDED ERGONOMICS: A CASE STUDY AT BDTSC TEXTILE FIRM

    Directory of Open Access Journals (Sweden)

    Amare Matebu

    2014-12-01

    Full Text Available Designing of lifting, pushing and pulling activities based on the physical and physiological capabilities of the operators is essential. The purpose of this study is to analyze manual material handling (MMH working posture of the operators using 3D Static Strength Prediction Program (3DSSPP software and to identify major areas causing long last injury of operators. The research has investigated the fit between the demands of tasks and the capabilities of operators. At the existing situations, the actual capabilities of operators have been computed with the help of 3DSSPP software and compared with NIOSH standards. Accordingly, operators' working posture is at an unacceptable position that exposes them for musculoskeletal disorders. Then, after the improvement of the design of MMH device (cart's roller, the result showed that the forces required by the operators to push and pull the sliver cans have been reduced from 931.77 Newton to 194.23 Newton. Furthermore, improvement of MMH cart's roller has reduced the awkward posture of operators and the risk of musculoskeletal disorders. The improved manual material handling design also saves about 1828.40 ETB per month for the company.

  15. Equipment Qualification Data Base user manual

    International Nuclear Information System (INIS)

    Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

    1985-09-01

    This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

  16. PFP MICON maintenance manual. Revision 1

    International Nuclear Information System (INIS)

    Silvan, G.R.

    1995-01-01

    This manual covers the use of maintenance displays, maintenance procedures, system alarms and common system failures. This manual is intended to supplement the MICON maintenance training not replace it. It also assumes that the user is familiar with the normal operation of the MICON A/S system. The MICON system is a distributed control computer and, among other things, controls the HVAC system for the Plutonium Finishing Plant

  17. STAIRS User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Gadjokov, V; Dragulev, V; Gove, N; Schmid, H

    1976-10-15

    The STorage And Information Retrieval System (STAIRS) of IBM is described from the user's point of view. The description is based on the experimental use of STAIRS at the IAEA computer, with INIS and AGRIS data bases, from June 1975 to May 1976. Special attention is paid to what may be termed the hierarchical approach to retrieval in STAIRS. Such an approach allows for better use of the intrinsic data-base structure and, hence, contributes to higher recall and/or relevance ratios in retrieval. The functions carried out by STAIRS are explained and the communication language between the user and the system outlined. Details are given of the specific structure of the INIS and AGRIS data bases for STAIRS. The manual should enable an inexperienced user to start his first on-line dialogues by means of a CRT or teletype terminal. (author)

  18. STAIRS User's Manual

    International Nuclear Information System (INIS)

    Gadjokov, V.; Dragulev, V.; Gove, N.; Schmid, H.

    1976-10-01

    The STorage And Information Retrieval System (STAIRS) of IBM is described from the user's point of view. The description is based on the experimental use of STAIRS at the IAEA computer, with INIS and AGRIS data bases, from June 1975 to May 1976. Special attention is paid to what may be termed the hierarchical approach to retrieval in STAIRS. Such an approach allows for better use of the intrinsic data-base structure and, hence, contributes to higher recall and/or relevance ratios in retrieval. The functions carried out by STAIRS are explained and the communication language between the user and the system outlined. Details are given of the specific structure of the INIS and AGRIS data bases for STAIRS. The manual should enable an inexperienced user to start his first on-line dialogues by means of a CRT or teletype terminal. (author)

  19. MELCOR computer code manuals

    Energy Technology Data Exchange (ETDEWEB)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

    1995-03-01

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

  20. MELCOR computer code manuals

    International Nuclear Information System (INIS)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

    1995-03-01

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

  1. ARDS User Manual

    Science.gov (United States)

    Fleming, David P.

    2001-01-01

    Personal computers (PCs) are now used extensively for engineering analysis. their capability exceeds that of mainframe computers of only a few years ago. Programs originally written for mainframes have been ported to PCs to make their use easier. One of these programs is ARDS (Analysis of Rotor Dynamic Systems) which was developed at Arizona State University (ASU) by Nelson et al. to quickly and accurately analyze rotor steady state and transient response using the method of component mode synthesis. The original ARDS program was ported to the PC in 1995. Several extensions were made at ASU to increase the capability of mainframe ARDS. These extensions have also been incorporated into the PC version of ARDS. Each mainframe extension had its own user manual generally covering only that extension. Thus to exploit the full capability of ARDS required a large set of user manuals. Moreover, necessary changes and enhancements for PC ARDS were undocumented. The present document is intended to remedy those problems by combining all pertinent information needed for the use of PC ARDS into one volume.

  2. Preliminary clinical experience with a dedicated interventional robotic system for CT-guided biopsies of lung lesions: a comparison with the conventional manual technique

    International Nuclear Information System (INIS)

    Anzidei, Michele; Argiro, Renato; Porfiri, Andrea; Boni, Fabrizio; Zaccagna, Fulvio; Napoli, Alessandro; Leonardi, Andrea; Bezzi, Mario; Catalano, Carlo; Anile, Marco; Venuta, Federico; Vitolo, Domenico; Saba, Luca; Longo, Flavia

    2015-01-01

    Evaluate the performance of a robotic system for CT-guided lung biopsy in comparison to the conventional manual technique. One hundred patients referred for CT-guided lung biopsy were randomly assigned to group A (robot-assisted procedure) or group B (conventional procedure). Size, distance from entry point and position in lung of target lesions were evaluated to assess homogeneity differences between the two groups. Procedure duration, dose length product (DLP), precision of needle positioning, diagnostic performance of the biopsy and rate of complications were evaluated to assess the clinical performance of the robotic system as compared to the conventional technique. All biopsies were successfully performed. The size (p = 0.41), distance from entry point (p = 0.86) and position in lung (p = 0.32) of target lesions were similar in both groups (p = 0.05). Procedure duration and radiation dose were significantly reduced in group A as compared to group B (p = 0.001). Precision of needle positioning, diagnostic performance of the biopsy and rate of complications were similar in both groups (p = 0.05). Robot-assisted CT-guided lung biopsy can be performed safely and with high diagnostic accuracy, reducing procedure duration and radiation dose in comparison to the conventional manual technique. (orig.)

  3. Preliminary clinical experience with a dedicated interventional robotic system for CT-guided biopsies of lung lesions: a comparison with the conventional manual technique

    Energy Technology Data Exchange (ETDEWEB)

    Anzidei, Michele; Argiro, Renato; Porfiri, Andrea; Boni, Fabrizio; Zaccagna, Fulvio; Napoli, Alessandro; Leonardi, Andrea; Bezzi, Mario; Catalano, Carlo [University of Rome, Department of Radiological, Oncological and Anatomopathological Sciences - Radiology - Sapienza, Rome (Italy); Anile, Marco; Venuta, Federico [University of Rome, Department of Thoracic Surgery - Sapienza, Rome (Italy); Vitolo, Domenico [University of Rome, Department of Radiological, Oncological and Anatomopathological Sciences - Pathology - Sapienza, Rome (Italy); Saba, Luca [Department of Radiology, Azienda Ospedaliero Universitaria (A.O.U.), di Cagliari-Polo di Monserrato, Monserrato (Italy); Longo, Flavia [University of Rome, Department of Radiological, Oncological and Anatomopathological Sciences - Oncology - Sapienza, Rome (Italy)

    2015-05-01

    Evaluate the performance of a robotic system for CT-guided lung biopsy in comparison to the conventional manual technique. One hundred patients referred for CT-guided lung biopsy were randomly assigned to group A (robot-assisted procedure) or group B (conventional procedure). Size, distance from entry point and position in lung of target lesions were evaluated to assess homogeneity differences between the two groups. Procedure duration, dose length product (DLP), precision of needle positioning, diagnostic performance of the biopsy and rate of complications were evaluated to assess the clinical performance of the robotic system as compared to the conventional technique. All biopsies were successfully performed. The size (p = 0.41), distance from entry point (p = 0.86) and position in lung (p = 0.32) of target lesions were similar in both groups (p = 0.05). Procedure duration and radiation dose were significantly reduced in group A as compared to group B (p = 0.001). Precision of needle positioning, diagnostic performance of the biopsy and rate of complications were similar in both groups (p = 0.05). Robot-assisted CT-guided lung biopsy can be performed safely and with high diagnostic accuracy, reducing procedure duration and radiation dose in comparison to the conventional manual technique. (orig.)

  4. Reliability and cross-cultural validation of the Turkish version of Manual Ability Classification System (MACS) for children with cerebral palsy.

    Science.gov (United States)

    Akpinar, Pinar; Tezel, Canan G; Eliasson, Ann-Christin; Icagasioglu, Afitap

    2010-01-01

    To determine the reliability and cross-cultural validation of the Turkish translation of the Manual Ability Classification System (MACS) for children with cerebral palsy (CP) and to investigate the relation to gross motor function and other comorbidities. After the forward and backward translation procedures, inter-rater and test-retest reliability was assessed between parents, physiotherapists and physicians using the intra-class correlation coefficient (ICC). Children (N = 118, 4 to 18 years, mean age 9 years 4 months; 68 boys, 50 girls) with various types of CP were classified. Additional data on the Gross Motor Function Classification System (GMFCS), intellectual delay, visual acuity, and epilepsy were collected. The inter-rater reliability was high; the ICC ranged from 0.89 to 0.96 among different professionals and parents. Between two persons of the same profession it ranged from 0.97 to 0.98. For the test-retest reliability it ranged from 0.91 to 0.98. Total agreement between the GMFCS and the MACS occurred in only 45% of the children. The level of the MACS was found to correlate with the accompanying comorbidities, namely intellectual delay and epilepsy. The Turkish version of the MACS is found to be valid and reliable, and is suggested to be appropriate for the assessment of manual ability within the Turkish population.

  5. Davis PV plant operation and maintenance manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This operation and maintenance manual contains the information necessary to run the Photovoltaics for Utility Scale Applications (PVUSA) test facility in Davis, California. References to more specific information available in drawings, data sheets, files, or vendor manuals are included. The PVUSA is a national cooperative research and demonstration program formed in 1987 to assess the potential of utility scale photovoltaic systems.

  6. Sierra Structural Dynamics Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Reese, Garth M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-19

    Sierra/SD provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of structural systems. This manual describes the theory behind many of the constructs in Sierra/SD. For a more detailed description of how to use Sierra/SD , we refer the reader to Sierra/SD, User's Notes . Many of the constructs in Sierra/SD are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Sierra/SD are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programmer notes manual, the user's notes and of course the material in the open literature. This page intentionally left blank.

  7. Attrition Cost Model Instruction Manual

    Science.gov (United States)

    Yanagiura, Takeshi

    2012-01-01

    This instruction manual explains in detail how to use the Attrition Cost Model program, which estimates the cost of student attrition for a state's higher education system. Programmed with SAS, this model allows users to instantly calculate the cost of attrition and the cumulative attrition rate that is based on the most recent retention and…

  8. Quality manual. Nuclear Regulatory Authority of the Slovak Republic

    International Nuclear Information System (INIS)

    2006-03-01

    This quality manual of the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. Basic characteristics of the UJD, Quality manual operative control, and Quality management system (QMS) are described. Management responsibility, Processes realization, Measurement, analysis (assessment) and improvement of the quality management system, Cancellation provision as well as abbreviations used in the Quality Manual are presented.

  9. Manual versus automated streaking system in clinical microbiology laboratory: Performance evaluation of Previ Isola for blood culture and body fluid samples.

    Science.gov (United States)

    Choi, Qute; Kim, Hyun Jin; Kim, Jong Wan; Kwon, Gye Cheol; Koo, Sun Hoe

    2018-01-04

    The process of plate streaking has been automated to improve routine workflow of clinical microbiology laboratories. Although there were many evaluation reports about the inoculation of various body fluid samples, few evaluations have been reported for blood. In this study, we evaluated the performance of automated inoculating system, Previ Isola for various routine clinical samples including blood. Blood culture, body fluid, and urine samples were collected. All samples were inoculated on both sheep blood agar plate (BAP) and MacConkey agar plate (MCK) using Previ Isola and manual method. We compared two methods in aspect of quality and quantity of cultures, and sample processing time. To ensure objective colony counting, an enumeration reading reference was made through a preliminary experiment. A total of 377 nonduplicate samples (102 blood culture, 203 urine, 72 body fluid) were collected and inoculated. The concordance rate of quality was 100%, 97.0%, and 98.6% in blood, urine, and other body fluids, respectively. In quantitative aspect, it was 98.0%, 97.0%, and 95.8%, respectively. The Previ Isola took a little longer to inoculate the specimen than manual method, but the hands-on time decreased dramatically. The shortened hands-on time using Previ Isola was about 6 minutes per 10 samples. We demonstrated that the Previ Isola showed high concordance with the manual method in the inoculation of various body fluids, especially in blood culture sample. The use of Previ Isola in clinical microbiology laboratories is expected to save considerable time and human resources. © 2018 Wiley Periodicals, Inc.

  10. A controlled trial of an expert system and self-help manual intervention based on the stages of change versus standard self-help materials in smoking cessation.

    Science.gov (United States)

    Aveyard, Paul; Griffin, Carl; Lawrence, Terry; Cheng, K K

    2003-03-01

    To examine the population impact and effectiveness of the Pro-Change smoking cessation course based on the Transtheoretical Model (TTM) compared to standard self-help smoking cessation literature. Randomized controlled trial. Sixty-five West Midlands general practices. Randomly sampled patients recorded as smokers by their general practitioners received an invitation letter and 2471 current smokers agreed. Responders were randomized to one of four interventions. The control group received standard self-help literature. In the Manual intervention group, participants received the Pro-Change system, a self-help workbook and three questionnaires at 3-monthly intervals, which generated individually tailored feedback. In the Phone intervention group, participants received the Manual intervention plus three telephone calls. In the Nurse intervention group, participants received the Manual intervention plus three visits to the practice nurse. Biochemically confirmed point prevalence of being quit and 6-month sustained abstinence, 12 months after study commencement. A total of 9.1% of registered current smokers participated, of whom 83.0% were not ready to quit. Less than half of participants returned questionnaires to generate second and third individualized feedback. Telephone calls reached 75% of those scheduled, but few participants visited the nurse. There were small differences between the three Pro-Change arms. The odds ratio (95% confidence intervals) for all Pro-Change arms combined versus the control arm were 1.50 (0.85-2.67) and 1.53 (0.76-3.10), for point prevalence and 6-month abstinence, respectively. This constitutes 2.1% of the TTM group versus 1.4% of the control group achieving confirmed 6-month sustained abstinence. There was no statistically significant benefit of the intervention apparent in this trial and the high relapse of quitters means that any population impact is small.

  11. Evaluation of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station

    International Nuclear Information System (INIS)

    Anderson, Michael T.; Diaz, Aaron A.; Doctor, Steven R.

    2012-01-01

    During a recent inservice inspection (ISI) of a dissimilar metal weld (DMW) in an inlet (hot leg) steam generator nozzle at North Anna Power Station Unit 1, several axially oriented flaws went undetected by the licensee's manual ultrasonic testing (UT) technique. The flaws were subsequently detected as a result of outside diameter (OD) surface machining in preparation for a full structural weld overlay. The machining operation uncovered the existence of two through-wall flaws, based on the observance of primary water leaking from the DMW. Further ultrasonic tests were then performed, and a total of five axially oriented flaws, classified as primary water stress corrosion cracking (PWSCC), were detected in varied locations around the weld circumference.

  12. Comparison of QIAsymphony automated and QIAamp manual DNA extraction systems for measuring Epstein-Barr virus DNA load in whole blood using real-time PCR.

    Science.gov (United States)

    Laus, Stella; Kingsley, Lawrence A; Green, Michael; Wadowsky, Robert M

    2011-11-01

    Automated and manual extraction systems have been used with real-time PCR for quantification of Epstein-Barr virus [human herpesvirus 4 (HHV-4)] DNA in whole blood, but few studies have evaluated relative performances. In the present study, the automated QIAsymphony and manual QIAamp extraction systems (Qiagen, Valencia, CA) were assessed using paired aliquots derived from clinical whole-blood specimens and an in-house, real-time PCR assay. The detection limits using the QIAsymphony and QIAamp systems were similar (270 and 560 copies/mL, respectively). For samples estimated as having ≥10,000 copies/mL, the intrarun and interrun variations were significantly lower using QIAsymphony (10.0% and 6.8%, respectively), compared with QIAamp (18.6% and 15.2%, respectively); for samples having ≤1000 copies/mL, the two variations ranged from 27.9% to 43.9% and were not significantly different between the two systems. Among 68 paired clinical samples, 48 pairs yielded viral loads ≥1000 copies/mL under both extraction systems. Although the logarithmic linear correlation from these positive samples was high (r(2) = 0.957), the values obtained using QIAsymphony were on average 0.2 log copies/mL higher than those obtained using QIAamp. Thus, the QIAsymphony and QIAamp systems provide similar EBV DNA load values in whole blood. Copyright © 2011 American Society for Investigative Pathology and the Association for Molecular Pathology. Published by Elsevier Inc. All rights reserved.

  13. CONHOR. Code system for determination of power distribution and burnup for the HOR reactor. Version 1.0.. User's manual

    International Nuclear Information System (INIS)

    Serov, I.V.; Hoogenboom, J.E.

    1993-07-01

    The main calculational tool is the CITATION code. CITATION is used for both static and burnup calculations. The pointwise flux density and power distributions obtained from these calculations are used to obtain the values of the desired quantities at the beginning of a burnup cycle. To obtain the most trustful values of the desired quantities CONHOR employs experimental information together with the CITATION calculated flux distributions. Axially averaged foil activation rates are obtained based on both CITATION pointwise flux density distributions and measured foil activity counts. These two sets of activation rates are called the distributions of auxiliary quantities and are compared with each other in order to pick up the corrections to the U-235 number densities in fuel containing elements. The methodical corrections to the calculational auxiliary quantities are obtained on this basis as well. They are used to obtain the methodical corrections to the desired quantities. The corrected desired quantities are the recommended ones. The correction procedure requires the knowledge of the sensitivity coefficients of the average foil activation rates with respect to the U-235 number densities (through the text of this manual U-235 is denoted also and especially in the input-output description sections as a BUrning-COrrected material, or 'BuCo' material). These sensitivity coefficients are calculated by the CONHOR SENS module. CITATION is employed to perform the calculations with perturbed values of U-235 number densities. Burnup calculations can be performed being based on either corrected or uncorrected U-235 number densities. Through the text of this manual XXXX means a 4-symbol identification of the burnup cycle to be studied. XX-1 and XX+1 mean correspondingly the previous and the following cycles. (orig./HP)

  14. User's manual of Tokamak Simulation Code

    International Nuclear Information System (INIS)

    Nakamura, Yukiharu; Nishino, Tooru; Tsunematsu, Toshihide; Sugihara, Masayoshi.

    1992-12-01

    User's manual for use of Tokamak Simulation Code (TSC), which simulates the time-evolutional process of deformable motion of axisymmetric toroidal plasma, is summarized. For the use at JAERI computer system, the TSC is linked with the data management system GAEA. This manual is forcused on the procedure for the input and output by using the GAEA system. Model equations to give axisymmetric motion, outline of code system, optimal method to get the well converged solution are also described. (author)

  15. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 1: Chapters 1-11

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    As a continuation of its effort to provide comprehensive and impartial guidance to Member States facing the need for introducing nuclear power, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package for carrying out power generation expansion planning studies. WASP was originally developed in 1972 in the USA to meet the IAEA's needs to analyze the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or region. The model was first used by the IAEA to conduct global studies (Market Survey for Nuclear Power Plants in Developing Countries, 1972-1973) and to carry out Nuclear Power Planning Studies for several Member States. The WASP system developed into a very comprehensive planning tool for electric power system expansion analysis. Following these developments, the so-called WASP-Ill version was produced in 1979. This version introduced important improvements to the system, namely in the treatment of hydroelectric power plants. The WASP-III version has been continually updated and maintained in order to incorporate needed enhancements. In 1981, the Model for Analysis of Energy Demand (MAED) was developed in order to allow the determination of electricity demand, consistent with the overall requirements for final energy, and thus, to provide a more adequate forecast of electricity needs to be considered in the WASP study. MAED and WASP have been used by the Agency for the conduct of Energy and Nuclear Power Planning Studies for interested Member States. More recently, the VALORAGUA model was completed in 1992 as a means for helping in the preparation of the hydro plant characteristics to be input in the WASP study and to verify that the WASP overall optimized expansion plan takes also into account an optimization of the use of water for electricity generation. The combined application of VALORAGUA and WASP permits the

  16. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 1: Chapters 1-11

    International Nuclear Information System (INIS)

    1995-01-01

    As a continuation of its effort to provide comprehensive and impartial guidance to Member States facing the need for introducing nuclear power, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package for carrying out power generation expansion planning studies. WASP was originally developed in 1972 in the USA to meet the IAEA's needs to analyze the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or region. The model was first used by the IAEA to conduct global studies (Market Survey for Nuclear Power Plants in Developing Countries, 1972-1973) and to carry out Nuclear Power Planning Studies for several Member States. The WASP system developed into a very comprehensive planning tool for electric power system expansion analysis. Following these developments, the so-called WASP-Ill version was produced in 1979. This version introduced important improvements to the system, namely in the treatment of hydroelectric power plants. The WASP-III version has been continually updated and maintained in order to incorporate needed enhancements. In 1981, the Model for Analysis of Energy Demand (MAED) was developed in order to allow the determination of electricity demand, consistent with the overall requirements for final energy, and thus, to provide a more adequate forecast of electricity needs to be considered in the WASP study. MAED and WASP have been used by the Agency for the conduct of Energy and Nuclear Power Planning Studies for interested Member States. More recently, the VALORAGUA model was completed in 1992 as a means for helping in the preparation of the hydro plant characteristics to be input in the WASP study and to verify that the WASP overall optimized expansion plan takes also into account an optimization of the use of water for electricity generation. The combined application of VALORAGUA and WASP permits the

  17. CSTEM User Manual

    Science.gov (United States)

    Hartle, M.; McKnight, R. L.

    2000-01-01

    This manual is a combination of a user manual, theory manual, and programmer manual. The reader is assumed to have some previous exposure to the finite element method. This manual is written with the idea that the CSTEM (Coupled Structural Thermal Electromagnetic-Computer Code) user needs to have a basic understanding of what the code is actually doing in order to properly use the code. For that reason, the underlying theory and methods used in the code are described to a basic level of detail. The manual gives an overview of the CSTEM code: how the code came into existence, a basic description of what the code does, and the order in which it happens (a flowchart). Appendices provide a listing and very brief description of every file used by the CSTEM code, including the type of file it is, what routine regularly accesses the file, and what routine opens the file, as well as special features included in CSTEM.

  18. GANDALF: users' manual

    International Nuclear Information System (INIS)

    Strout, R.E. II; Beach, J.L.

    1977-01-01

    The GANDALF computer code was written to calculate neutron dose equivalent given the pulse-height data obtained by using a Linear Energy Transfer (LET) proportional counter. The code also uses pre- and/or post-calibration spectra, from an alpha source, to determine a calibration factor in keV/μ/channel. Output from the code consists of the effective radius of the detection chamber in microns, a calibration factor in keV/μ/channel, and the total dose and dose equivalent in rad or rem between any two LET energies by using the equations by Attix and Roesch [Radiation Dosimetry, 1, 71 (1968)]. This report is a user's manual and is not intended as anything else, and assumes that the user has a basic knowledge of the LLL Octopus timesharing system. However, a very brief description of how the code operates is included

  19. FRMAC Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Frandsen, K.

    2010-05-01

    In the event of a major radiological incident, the Federal Radiological Monitoring and Assessment Center (FRMAC) will coordinate the federal agencies that have various statutory responsibilities. The FRMAC is responsible for coordinating all environmental radiological monitoring, sampling, and assessment activities for the response. This manual describes the FRMAC’s response activities in a radiological incident. It also outlines how FRMAC fits in the National Incident Management System (NIMS) under the National Response Framework (NRF) and describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the affected areas. In the event of a potential or existing major radiological incident, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is responsible for establishing and managing the FRMAC during the initial phases.

  20. Culture expansion of adipose derived stromal cells. A closed automated Quantum Cell Expansion System compared with manual flask-based culture

    Directory of Open Access Journals (Sweden)

    Mandana Haack-Sørensen

    2016-11-01

    Full Text Available Abstract Background Adipose derived stromal cells (ASCs are a rich and convenient source of cells for clinical regenerative therapeutic approaches. However, applications of ASCs often require cell expansion to reach the needed dose. In this study, cultivation of ASCs from stromal vascular fraction (SVF over two passages in the automated and functionally closed Quantum Cell Expansion System (Quantum system is compared with traditional manual cultivation. Methods Stromal vascular fraction was isolated from abdominal fat, suspended in α-MEM supplemented with 10% Fetal Bovine Serum and seeded into either T75 flasks or a Quantum system that had been coated with cryoprecipitate. The cultivation of ASCs from SVF was performed in 3 ways: flask to flask; flask to Quantum system; and Quantum system to Quantum system. In all cases, quality controls were conducted for sterility, mycoplasmas, and endotoxins, in addition to the assessment of cell counts, viability, immunophenotype, and differentiation potential. Results The viability of ASCs passage 0 (P0 and P1 was above 96%, regardless of cultivation in flasks or Quantum system. Expression of surface markers and differentiation potential was consistent with ISCT/IFATS standards for the ASC phenotype. Sterility, mycoplasma, and endotoxin tests were consistently negative. An average of 8.0 × 107 SVF cells loaded into a Quantum system yielded 8.96 × 107 ASCs P0, while 4.5 × 106 SVF cells seeded per T75 flask yielded an average of 2.37 × 106 ASCs—less than the number of SVF cells seeded. ASCs P1 expanded in the Quantum system demonstrated a population doubling (PD around 2.2 regardless of whether P0 was previously cultured in flasks or Quantum, while ASCs P1 in flasks only reached a PD of 1.0. Conclusion: Manufacturing of ASCs in a Quantum system enhances ASC expansion rate and yield significantly relative to manual processing in T-flasks, while maintaining the purity and quality essential to

  1. Culture expansion of adipose derived stromal cells. A closed automated Quantum Cell Expansion System compared with manual flask-based culture.

    Science.gov (United States)

    Haack-Sørensen, Mandana; Follin, Bjarke; Juhl, Morten; Brorsen, Sonja K; Søndergaard, Rebekka H; Kastrup, Jens; Ekblond, Annette

    2016-11-16

    Adipose derived stromal cells (ASCs) are a rich and convenient source of cells for clinical regenerative therapeutic approaches. However, applications of ASCs often require cell expansion to reach the needed dose. In this study, cultivation of ASCs from stromal vascular fraction (SVF) over two passages in the automated and functionally closed Quantum Cell Expansion System (Quantum system) is compared with traditional manual cultivation. Stromal vascular fraction was isolated from abdominal fat, suspended in α-MEM supplemented with 10% Fetal Bovine Serum and seeded into either T75 flasks or a Quantum system that had been coated with cryoprecipitate. The cultivation of ASCs from SVF was performed in 3 ways: flask to flask; flask to Quantum system; and Quantum system to Quantum system. In all cases, quality controls were conducted for sterility, mycoplasmas, and endotoxins, in addition to the assessment of cell counts, viability, immunophenotype, and differentiation potential. The viability of ASCs passage 0 (P0) and P1 was above 96%, regardless of cultivation in flasks or Quantum system. Expression of surface markers and differentiation potential was consistent with ISCT/IFATS standards for the ASC phenotype. Sterility, mycoplasma, and endotoxin tests were consistently negative. An average of 8.0 × 10 7 SVF cells loaded into a Quantum system yielded 8.96 × 10 7 ASCs P0, while 4.5 × 10 6 SVF cells seeded per T75 flask yielded an average of 2.37 × 10 6 ASCs-less than the number of SVF cells seeded. ASCs P1 expanded in the Quantum system demonstrated a population doubling (PD) around 2.2 regardless of whether P0 was previously cultured in flasks or Quantum, while ASCs P1 in flasks only reached a PD of 1.0. Manufacturing of ASCs in a Quantum system enhances ASC expansion rate and yield significantly relative to manual processing in T-flasks, while maintaining the purity and quality essential to safe and robust cell production. Notably, the use of the Quantum

  2. Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  3. Radiological Control Manual

    International Nuclear Information System (INIS)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

  4. HASL procedures manual

    International Nuclear Information System (INIS)

    Harley, J.H.

    1977-08-01

    Additions and corrections to the following sections of the HASL Procedures Manual are provided: General, Sampling, Field Measurements; General Analytical Chemistry, Chemical Procedures, Data Section, and Specifications

  5. PCs The Missing Manual

    CERN Document Server

    Karp, David

    2005-01-01

    Your vacuum comes with one. Even your blender comes with one. But your PC--something that costs a whole lot more and is likely to be used daily and for tasks of far greater importance and complexity--doesn't come with a printed manual. Thankfully, that's not a problem any longer: PCs: The Missing Manual explains everything you need to know about PCs, both inside and out, and how to keep them running smoothly and working the way you want them to work. A complete PC manual for both beginners and power users, PCs: The Missing Manual has something for everyone. PC novices will appreciate the una

  6. TRANSWRAP II: problem definition manual

    International Nuclear Information System (INIS)

    Knittle, D.E.

    1981-02-01

    The TRANSWRAP II computer code, written in Fortran IV and described in this Problem Definition Manual, was developed to analytically predict the magnitude of pressure pulses of large scale sodium-wate reactions in LMFBR secondary systems. It is currently being used for the Clinch River Breeder Reactor Program. The code provides the options, flexibility and features necessary to consider any system configuration. The code methodology has been validated with the aid of extensive sodium-water reaction test programs

  7. Towards Automatic Capturing of Manual Data Processing Provenance

    NARCIS (Netherlands)

    Wombacher, Andreas; Huq, M.R.

    2011-01-01

    Often data processing is not implemented by a work ow system or an integration application but is performed manually by humans along the lines of a more or less specified procedure. Collecting provenance information during manual data processing can not be automated. Further, manual collection of

  8. Nuclear medicine resources manual

    International Nuclear Information System (INIS)

    2006-02-01

    Over the past decade many IAEA programmes have significantly enhanced the capabilities of numerous Member States in the field of nuclear medicine. Functional imaging using nuclear medicine procedures has become an indispensable tool for the diagnosis, treatment planning and management of patients. However, due to the heterogeneous growth and development of nuclear medicine in the IAEA's Member States, the operating standards of practice vary considerably from country to country and region to region. This publication is the result of the work of over 30 international professionals who have assisted the IAEA in the process of standardization and harmonization. This manual sets out the prerequisites for the establishment of a nuclear medicine service, including basic infrastructure, suitable premises, reliable supply of electricity, maintenance of a steady temperature, dust exclusion for gamma cameras and radiopharmacy dispensaries. It offers clear guidance on human resources and training needs for medical doctors, technologists, radiopharmaceutical scientists, physicists and specialist nurses in the practice of nuclear medicine. The manual describes the requirements for safe preparation and quality control of radiopharmaceuticals. In addition, it contains essential requirements for maintenance of facilities and instruments, for radiation hygiene and for optimization of nuclear medicine operational performance with the use of working clinical protocols. The result is a comprehensive guide at an international level that contains practical suggestions based on the experience of professionals around the globe. This publication will be of interest to nuclear medicine physicians, radiologists, medical educationalists, diagnostic centre managers, medical physicists, medical technologists, radiopharmacists, specialist nurses, clinical scientists and those engaged in quality assurance and control systems in public health in both developed and developing countries

  9. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0: Models and Results Database (MAR-D) reference manual. Volume 8

    International Nuclear Information System (INIS)

    Russell, K.D.; Skinner, N.L.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The primary function of MAR-D is to create a data repository for completed PRAs and Individual Plant Examinations (IPEs) by providing input, conversion, and output capabilities for data used by IRRAS, SARA, SETS, and FRANTIC software. As probabilistic risk assessments and individual plant examinations are submitted to the NRC for review, MAR-D can be used to convert the models and results from the study for use with IRRAS and SARA. Then, these data can be easily accessed by future studies and will be in a form that will enhance the analysis process. This reference manual provides an overview of the functions available within MAR-D and step-by-step operating instructions

  10. User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents.

    Science.gov (United States)

    Shachak, Aviv; Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R; Lemieux-Charles, Louise

    2013-06-04

    Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and adapted to specific organizational contexts and workflows. The main limitation of the study

  11. User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents

    Science.gov (United States)

    Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R.; Lemieux-Charles, Louise

    2015-01-01

    Research problem Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. Research question What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Literature review Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. Methodology We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. Results and discussion The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and

  12. Oil Spill Response Manual

    NARCIS (Netherlands)

    Marieke Zeinstra; Sandra Heins; Wierd Koops

    2014-01-01

    A two year programme has been carried out by the NHL University of Applied Sciences together with private companies in the field of oil and chemical spill response to finalize these manuals on oil and chemical spill response. These manuals give a good overview of all aspects of oil and chemical

  13. Technical Manual. The ACT®

    Science.gov (United States)

    ACT, Inc., 2014

    2014-01-01

    This manual contains technical information about the ACT® college readiness assessment. The principal purpose of this manual is to document the technical characteristics of the ACT in light of its intended purposes. ACT regularly conducts research as part of the ongoing formative evaluation of its programs. The research is intended to ensure that…

  14. Eco-Innovation Manual

    DEFF Research Database (Denmark)

    O'Hare, Jamie Alexander; McAloone, Tim C.; Pigosso, Daniela Cristina Antelmi

    Aim of this manual is to introduce a methodology for the implementation of eco‐innovation within small and medium sized companies in developing and emerging economies. The intended audience of this manual is organizations that provide professional services to guide and support manufacturing compa...... companies to improve their sustainability performance....

  15. Marketing Research. Instructor's Manual.

    Science.gov (United States)

    Small Business Administration, Washington, DC.

    Prepared for the Administrative Management Course Program, this instructor's manual was developed to serve small-business management needs. The sections of the manual are as follows: (1) Lesson Plan--an outline of material covered, which may be used as a teaching guide, presented in two columns: the presentation, and a step-by-step indication of…

  16. Indoor Air Quality Manual.

    Science.gov (United States)

    Baldwin Union Free School District, NY.

    This manual identifies ways to improve a school's indoor air quality (IAQ) and discusses practical actions that can be carried out by school staff in managing air quality. The manual includes discussions of the many sources contributing to school indoor air pollution and the preventive planning for each including renovation and repair work,…

  17. GERTS GQ User's Manual.

    Science.gov (United States)

    Akiba, Y.; And Others

    This user's manual for the simulation program Graphical Evaluation and Review Technique (GERT) GQ contains sections on nodes, branches, program input description and format, and program output, as well as examples. Also included is a programmer's manual which contains information on scheduling, subroutine descriptions, COMMON Variables, and…

  18. CRISP instrument manual

    International Nuclear Information System (INIS)

    Bucknall, D.G.; Langridge, Sean

    1997-05-01

    This document is a user manual for CRISP, one of the two neutron reflectomers at ISIS. CRISP is highly automated allowing precision reproducible measurements. The manual provides detailed instructions for the setting-up and running of the instrument and advice on data analysis. (UK)

  19. Closed-loop double-vasopressor automated system vs manual bolus vasopressor to treat hypotension during spinal anaesthesia for caesarean section: a randomised controlled trial.

    Science.gov (United States)

    Sng, B L; Tan, H S; Sia, A T H

    2014-01-01

    Hypotension necessitating vasopressor administration occurs commonly during caesarean section under spinal anaesthesia. We developed a novel vasopressor delivery system that automatically administers phenylephrine or ephedrine based on continuous non-invasive arterial pressure monitoring. A phenylephrine bolus of 50 μg was given at 30-s intervals when systolic blood pressure fell manual boluses of either phenylephrine 100 μg or ephedrine 8 mg, administered at 1-min intervals based on the same thresholds for systolic pressure and heart rate. This randomised, controlled, double-blinded trial involved 213 healthy women who underwent elective caesarean delivery under spinal anaesthesia using 11 mg hyperbaric bupivacaine with 15 μg fentanyl and 100 μg morphine. The automated vasopressor group had better systolic pressure control, with 37/106 (34.9%) having any beat-to-beat systolic pressure reading 120% of baseline, with 8/106 (7.5%) in the automated vasopressor group vs 14/107 (13.1%) in the control group, or total dose of vasopressors. The automated vasopressor group had lower median absolute performance error of 8.5% vs control of 9.8% (p = 0.013), and reduced incidence of nausea (1/106 (0.9%) vs 11/107 (10.3%), p = 0.005). Neonatal umbilical cord pH, umbilical lactate and Apgar scores were similar. Hence, our system afforded better control of maternal blood pressure and reduced nausea with no increase in reactive hypertension when compared with manual boluses. © 2013 The Association of Anaesthetists of Great Britain and Ireland.

  20. User's Manual for CoEAT Tool

    Science.gov (United States)

    The Co-EAT users manual is designed to help the anaerobic digestion system operators evaluate the costs and benefits of accepting and processing wasted food, fats, oils and greases (FOG) or other organic materials.