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

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

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

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

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)

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

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

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

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)

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.

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)

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

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)

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.

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

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)

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

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

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

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)

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

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

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

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)

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

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)

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

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

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)

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.

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

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

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)

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)

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)

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

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

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

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

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.

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

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)

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)

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

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

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.

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

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

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.

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

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

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

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

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)

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)

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

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

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

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

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

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

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)

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

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

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

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

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)

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...

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…

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

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...

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'

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...

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...

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.

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

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…

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

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).

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....

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.

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

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…

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

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.

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

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.

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.

Sustainability of Advanced Fuel Cycles

International Nuclear Information System (INIS)

Kuznetsov, Vladimir

2013-01-01

⇒ The IAEA’s International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000. ⇒ INPRO cooperates with Member States to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. ⇒ INPRO is part of the integrated services of the IAEA provided to Member States considering initial development or expansion of nuclear energy programmes. ⇒ INPRO Methodology for nuclear energy system assessment - a comprehensive set of internationally agreed basic principles, requirements and criteria in the important areas of economics, safety, waste management, proliferation resistance, physical protection, environment and infrastructure. ⇒ Meeting the INPRO criteria in all of the areas ensures sustainability of nuclear energy system and its high potential to meet growing energy demand throughout the present century

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)…

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.

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

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.

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

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.

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

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

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.

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.

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.

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.

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.

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...

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

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...

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

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.

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...

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

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

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.

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…

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.

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

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

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

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

Heterogeneous world model and collaborative scenarios of transition to globally sustainable nuclear energy systems

Directory of Open Access Journals (Sweden)

Kuznetsov Vladimir

2015-01-01

Full Text Available The International Atomic Energy Agency's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO is to help ensure that nuclear energy is available to contribute to meeting global energy needs of the 21st century in a sustainable manner. The INPRO task titled “Global scenarios” is to develop global and regional nuclear energy scenarios that lead to a global vision of sustainable nuclear energy in the 21st century. Results of multiple studies show that the criteria for developing sustainable nuclear energy cannot be met without innovations in reactor and nuclear fuel cycle technologies. Combining different reactor types and associated fuel chains creates a multiplicity of nuclear energy system arrangements potentially contributing to global sustainability of nuclear energy. In this, cooperation among countries having different policy regarding fuel cycle back end would be essential to bring sustainability benefits from innovations in technology to all interested users. INPRO has developed heterogeneous global model to capture countries’ different policies regarding the back end of the nuclear fuel cycle in regional and global scenarios of nuclear energy evolution and applied in a number of studies performed by participants of the project. This paper will highlight the model and major conclusions obtained in the studies.

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.

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

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.

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.

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.

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

Heterogeneous world model and collaborative scenarios of transition to globally sustainable nuclear energy systems - 15483

International Nuclear Information System (INIS)

Kuznetsov, V.; Fesenko, G.

2015-01-01

The International Atomic Energy Agency's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) is to help ensure that nuclear energy is available to contribute to meeting global energy needs of the 21. century in a sustainable manner. The INPRO task titled 'Global scenarios' is to develop global and regional nuclear energy scenarios that lead to a global vision of sustainable nuclear energy in the 21. century. Results of multiple studies show that the criteria for developing sustainable nuclear energy cannot be met without innovations in reactor and nuclear fuel cycle technologies. Combining different reactor types and associated fuel chains creates a multiplicity of nuclear energy system arrangements potentially contributing to global sustainability of nuclear energy. In this, cooperation among countries having different policy regarding fuel cycle back end would be essential to bring sustainability benefits from innovations in technology to all interested users. INPRO has developed heterogeneous global model to capture countries' different policies regarding the back end of the nuclear fuel cycle in regional and global scenarios of nuclear energy evolution and applied in a number of studies performed by participants of the project. This paper will highlight the model and major conclusions obtained in the studies. (authors)

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

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

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.

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.)

Nuclear energy development in the 21st century: Global scenarios and regional trends

International Nuclear Information System (INIS)

2010-01-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in 2000, on the basis of a resolution of the IAEA General Conference (GC(44)/RES/21). INPRO helps ensure that sustainable nuclear energy is available in the twenty-first century and seeks to bring together all interested Member States - both technology holders and technology users - to consider joint actions to achieve desired innovations. As of July 2010, 30 countries and the European Commission are members of INPRO. Programme Area B of INPRO, Global Vision - Scenarios and Pathways to Sustainable Nuclear Power Development, is aimed at providing a better understanding of the role of nuclear energy in the context of long term sustainable development. Its objective is to develop 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 twenty-first century, and to support Member States in working towards that vision. This report presents the results of a study undertaken under Programme Area B in INPRO on Nuclear Energy Development in the Twenty-first Century: Global Scenarios and Regional Trends Studies on Nuclear Capacity Growth and Material Flow between Regions. The report does not develop a global vision for nuclear deployment per se, but presents a limited set of technical scenarios of nuclear deployment and considers their implications. It considers a global energy supply system composed of several reactor and fuel cycle types available today and of fast reactors that may be developed in the future to illustrate a possible modelling approach to identify the potential role of interregional transfer of nuclear fuel resources in supporting the global growth of nuclear energy. The study was performed with the participation of sixteen experts from nine INPRO Member States and included a dynamic simulation of material flows in nuclear energy systems using

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

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

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.

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.

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.

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

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.

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)

Evaluation of manual and automatic manually triggered ventilation performance and ergonomics using a simulation model.

Science.gov (United States)

Marjanovic, Nicolas; Le Floch, Soizig; Jaffrelot, Morgan; L'Her, Erwan

2014-05-01

In the absence of endotracheal intubation, the manual bag-valve-mask (BVM) is the most frequently used ventilation technique during resuscitation. The efficiency of other devices has been poorly studied. The bench-test study described here was designed to evaluate the effectiveness of an automatic, manually triggered system, and to compare it with manual BVM ventilation. A respiratory system bench model was assembled using a lung simulator connected to a manikin to simulate a patient with unprotected airways. Fifty health-care providers from different professional groups (emergency physicians, residents, advanced paramedics, nurses, and paramedics; n = 10 per group) evaluated manual BVM ventilation, and compared it with an automatic manually triggered device (EasyCPR). Three pathological situations were simulated (restrictive, obstructive, normal). Standard ventilation parameters were recorded; the ergonomics of the system were assessed by the health-care professionals using a standard numerical scale once the recordings were completed. The tidal volume fell within the standard range (400-600 mL) for 25.6% of breaths (0.6-45 breaths) using manual BVM ventilation, and for 28.6% of breaths (0.3-80 breaths) using the automatic manually triggered device (EasyCPR) (P < .0002). Peak inspiratory airway pressure was lower using the automatic manually triggered device (EasyCPR) (10.6 ± 5 vs 15.9 ± 10 cm H2O, P < .001). The ventilation rate fell consistently within the guidelines, in the case of the automatic manually triggered device (EasyCPR) only (10.3 ± 2 vs 17.6 ± 6, P < .001). Significant pulmonary overdistention was observed when using the manual BVM device during the normal and obstructive sequences. The nurses and paramedics considered the ergonomics of the automatic manually triggered device (EasyCPR) to be better than those of the manual device. The use of an automatic manually triggered device may improve ventilation efficiency and decrease the risk of

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

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).

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...

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

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.

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.

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.)

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

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

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

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.

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

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)

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.

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)

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

Acquisition/Diversion Pathway Analysis of the DUPIC Fuel Cycle for the Assessment of Proliferation Resistance

International Nuclear Information System (INIS)

Chang, Hong Lae; Ko, Won Il

2008-01-01

Within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) of the IAEA, a methodology for evaluating proliferation resistance (INPRO PR methodology) has been developed in order to provide guidance in using the INPRO methodology. However, it remains to develop the methodology to evaluate User Requirements (UR) 4 regarding multiplicity and robustness of barriers against proliferation (innovative nuclear energy systems should incorporate multiple proliferation resistance features and measures). To develop the assessment procedure and metrics for User Requirement 4 (UR4), the coarse acquisition/ diversion pathway analysis of the DUPIC Fuel Cycle has been performed. The most plausible pathways for the acquisition of weapons-usable nuclear material were identified and analyzed using a systematic approach herein, and future work to complete the assessment approach for the UR4 of the INPRO methodology regarding the multiplicity and robustness of barriers against proliferation are also proposed

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).

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.

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…

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

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

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

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.

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.

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

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...

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)

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)

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

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.

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.

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.

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.

Contents Development of Library Signage Manual in Korea

OpenAIRE

In-Ja Ahn

2011-01-01

There is an increase in the need of an unified manual for library signage system, due to recent increase in library construction or remodeling. This paper, therefore, can be a basic research to develop library signage system manual. Based on an anual released from KLA and the sum of opinions of expert groups, this research proposes a concrete list of contents for library signage system manual as follows. First, there is a need of theoretical basis of library signage system. Second, for the ac...

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.

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

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

Contents Development of Library Signage Manual in Korea

Directory of Open Access Journals (Sweden)

In-Ja Ahn

2011-12-01

Full Text Available There is an increase in the need of an unified manual for library signage system, due to recent increase in library construction or remodeling. This paper, therefore, can be a basic research to develop library signage system manual. Based on an anual released from KLA and the sum of opinions of expert groups, this research proposes a concrete list of contents for library signage system manual as follows. First, there is a need of theoretical basis of library signage system. Second, for the actual practices of signage system, planning, check list, and standard terms shall be necessary.

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

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.

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.

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)

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.

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

The Northern States Power Company welding manual advisor

International Nuclear Information System (INIS)

Lu, Yi; Wood, R.M.

1993-01-01

The Welding Manual Advisor (WMA) is an object oriented expert system designed to assist Northern States Power (NSP) personnel in implementing the company's Welding Manual. The expert system captures the knowledge of welding experts, addresses important issues in welding activities and automates the use of the Welding Manual. It is estimated that use of the WMA will save $81,000 over the next six years at NSP, because of the reduction of labor and errors in the use of the Welding Manual, and facilitation of training of NSP personnel. The important features of the WMA include the accuracy and consistency in determining welding procedure and requirements, update capability, user friendly interface, on-line help function, back-up capability, and well-documented manuals

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)

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

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.

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

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

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

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)

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.

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.

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

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)

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)

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)

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.

Peace Corps Aquaculture Training Manual. Training Manual T0057.

Science.gov (United States)

Peace Corps, Washington, DC. Information Collection and Exchange Div.

This Peace Corps training manual was developed from two existing manuals to provide a comprehensive training program in fish production for Peace Corps volunteers. The manual encompasses the essential elements of the University of Oklahoma program that has been training volunteers in aquaculture for 25 years. The 22 chapters of the manual are…

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).

Analytical framework for the analysis/assessment of transition scenarios to sustainable nuclear energy systems and its applications

International Nuclear Information System (INIS)

Kuznetsov, V.

2013-01-01

IAEA/INPRO (in cooperation with the IAEA's Planning and Economic Studies Section) have developed an internationally verified analytical framework to assist Member States in Nuclear energy development modelling, including material flow analysis, economic assessment and least cost model optimization (IAEA Nuclear Energy Series No. NP-T-1.14 in print). The INPRO Group (in cooperation with the IAEA's Planning and Economic Studies Section) provides training to Member States on mastering and application of this analytical framework to particular problems of national/ collaborative nuclear energy development. For small programmes of the fast reactors/closed nuclear fuel cycle deployment the economic benefits from their introduction would be substantially lower than the amount of investments needed for RD&D, licensing and deployment. Only a few countries in the world with large nuclear energy programmes (30 GW(e) for fast reactors) can bear the burden of the technology development for fast reactors/closed nuclear fuel cycle. Therefore, global nuclear energy system would follow a heterogeneous world model, at least, within the present century

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.

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

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.)

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.)

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).

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)

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.

Stepping motor control processor reference manual. Volume I

International Nuclear Information System (INIS)

Holloway, F.W.; VanArsdall, P.J.; Suski, G.J.; Gant, R.G.; Rash, M.

1980-01-01

This manual is intended to serve several purposes. The first goal is to describe the capabilities and operation of the SMC processor package from an operator or user point of view. Secondly, the manual will describe in some detail the basic hardware elements and how they can be used effectively to implement a step motor control system. Practical information on the use, installation and checkout of the hardware set is presented in the following sections along with programming suggestions. Available related system software is described in this manual for reference and as an aid in understanding the system architecture. Section two presents an overview and operations manual of the SMC processor describing its composition and functional capabilities. Section three contains hardware descriptions in some detail for the LLL-designed hardware used in the SMC processor. Basic theory of operation and important features are explained

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.

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.

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

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.

TA-55 change control manual

International Nuclear Information System (INIS)

Blum, T.W.; Selvage, R.D.; Courtney, K.H.

1997-11-01

This manual is the guide for initiating change at the Plutonium Facility, which handles the processing of plutonium as well as research on plutonium metallurgy. It describes the change and work control processes employed at TA-55 to ensure that all proposed changes are properly identified, reviewed, approved, implemented, tested, and documented so that operations are maintained within the approved safety envelope. All Laboratory groups, their contractors, and subcontractors doing work at TA-55 follow requirements set forth herein. This manual applies to all new and modified processes and experiments inside the TA-55 Plutonium Facility; general plant project (GPP) and line item funded construction projects at TA-55; temporary and permanent changes that directly or indirectly affect structures, systems, or components (SSCs) as described in the safety analysis, including Facility Control System (FCS) software; and major modifications to procedures. This manual does not apply to maintenance performed on process equipment or facility SSCs or the replacement of SSCs or equipment with documented approved equivalents

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)

Nuclear power newsletter. Vol. 7, no. 4, December 2010

International Nuclear Information System (INIS)

2010-12-01

The IAEA marked the 10th anniversary of INPRO on the opening day of the 54th IAEA General Conference in September 2010. IAEA Director General Yukiya Amano led the celebrations for INPRO, thanking the 31 members participating in the project for their support. Representatives from leading INPRO member states and partners expressed their support for the project

Requirements to be met by the operation manual

International Nuclear Information System (INIS)

1981-03-01

The rule applies to the contents and the lay-out of the operating manual for stationary nuclear power plants. The draft contains: 1. General requirement to be met by the contents of the operating manual. The operating manual to be arranged in 4 parts (part 1: internal rules and regulations; part 2: operation overall plant; part 3: incidents; part 4: operation systems). Safety specifications to be included in the manual, the exemption being the system of technical documentation. 2. General requirements to be met by the lay-out of the operating manual. Comprehensibility; legibility; structure and subdivisions; arrangement of the instructions and design of the manuals cover. 3. Requirements to be met by part 1. Defining the various internal rules and regulations (personnel management); rules and regulations concerning inspections and shift work; maintenance and repair; radiation protection; guard duty and admission; alarm; fire protection; first aid. 4. Requirements to be met by part 2. Provisions and operational limitations; limit values important from the point of view of safety; normal operation; anomalous operation; in-service inspections. 6. Requirements to be met by part 3. 7. Annex: Rules, regulations and stipulations mentioned in the rule draft. (orig.)

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

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.

Energy System Expectations for Nuclear in the 21. Century: A Plausible Range

International Nuclear Information System (INIS)

Langlois, Lucille M.; McDonald, Alan; Rogner, Hans-Holger; Vera, Ivan

2002-01-01

This paper outlines a range of scenarios describing what the world's energy system might look like in the middle of the century, and what nuclear energy's most profitable role might be. The starting point is the 40 non-greenhouse-gas-mitigation scenarios in the Special Report on Emissions Scenarios (SRES) of the Intergovernmental Panel on Climate Change (IPCC, 2000). Given their international authorship and comprehensive review by governments and scientific experts, the SRES scenarios are the state of the art in long-term energy scenarios. However, they do not present the underlying energy system structures in enough detail for specific energy technology and infrastructure analyses. This paper therefore describes initial steps within INPRO (The International Project on Innovative Nuclear Reactors and Fuel Cycles of the International Atomic Energy Agency) to translate the SRES results into a range of possible nuclear energy technology requirements for mid-century. The paper summarizes the four SRES scenarios that will be used in INPRO and the reasons for their selection. It provides illustrative examples of the sort of additional detail that is being developed about the overall energy system implied by each scenario, and about specific scenario features particularly relevant to nuclear energy. As recommended in SRES, the selected scenarios cover all four SRES 'story-line families'. The energy system translations being developed in INPRO are intended to indicate how energy services may be provided in mid-century and to delineate likely technology and infrastructure implications. They will indicate answers to questions like the following. The list is illustrative, not comprehensive. - What kind of nuclear power plants will best fit the mid-century energy system? - What energy forms and other products and services provided by nuclear reactors will best fit the mid-century energy system? - What would be their market shares? - How difficult will it be to site new nuclear

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

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)

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...

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.

Geothermal reservoir assessment manual; 1984-1992 nendo chinetsu choryusou hyoka shuhou manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-02-01

A geothermal reservoir assessment manual was prepared for the promotion of the development of geothermal power generation, based on the results of the 'geothermal reservoir assessment technique development project' implemented during the fiscal 1984-1992 period and on the results of surveys conducted in Japan and abroad. Of the geothermal systems generally classified into the steam dominant type and the hot water dominant type, encounters with the steam dominant type are but seldom reported. This manual therefore covers the hot water dominant type only. In addition to the explanation of the basic concept and the outline of geothermal reservoirs, the manual carries data necessary for reservoir assessment; geological and geophysical data analyses; geochemistry in reservoir assessment; data of underground logging and of fuming; conceptual models; simulators and models for reservoir simulation; natural-state simulation, history-matching simulation, and reservoir behavior predicting simulation; case history (modeling of a geothermal reservoir prior to exploitation), references, and so forth. (NEDO)

Geothermal reservoir assessment manual; 1984-1992 nendo chinetsu choryusou hyoka shuhou manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-02-01

A geothermal reservoir assessment manual was prepared for the promotion of the development of geothermal power generation, based on the results of the 'geothermal reservoir assessment technique development project' implemented during the fiscal 1984-1992 period and on the results of surveys conducted in Japan and abroad. Of the geothermal systems generally classified into the steam dominant type and the hot water dominant type, encounters with the steam dominant type are but seldom reported. This manual therefore covers the hot water dominant type only. In addition to the explanation of the basic concept and the outline of geothermal reservoirs, the manual carries data necessary for reservoir assessment; geological and geophysical data analyses; geochemistry in reservoir assessment; data of underground logging and of fuming; conceptual models; simulators and models for reservoir simulation; natural-state simulation, history-matching simulation, and reservoir behavior predicting simulation; case history (modeling of a geothermal reservoir prior to exploitation), references, and so forth. (NEDO)

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

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

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)

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.

Workshop on IAEA Tools for Nuclear Energy System Assessment for Long-Term Planning and Development

International Nuclear Information System (INIS)

2009-01-01

The purpose of the workshop is to present to Member States tools and methods that are available from the IAEA in support of long-term energy planning and nuclear energy system assessments, both focusing on the sustainable development of nuclear energy. This includes tools devoted to energy system planning, indicators for sustainable energy development, the INPRO methodology for Nuclear Energy System Assessment (NESA) and tools for analysing nuclear fuel cycle material balance. The workshop also intends to obtain feedback from Member States on applying the tools, share experiences and lessons learned, and identify needs for IAEA support

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.

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

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)

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

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

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

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.

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

Manual vs. computer-assisted sperm analysis: can CASA replace manual assessment of human semen in clinical practice?

Science.gov (United States)

Talarczyk-Desole, Joanna; Berger, Anna; Taszarek-Hauke, Grażyna; Hauke, Jan; Pawelczyk, Leszek; Jedrzejczak, Piotr

2017-01-01

The aim of the study was to check the quality of computer-assisted sperm analysis (CASA) system in comparison to the reference manual method as well as standardization of the computer-assisted semen assessment. The study was conducted between January and June 2015 at the Andrology Laboratory of the Division of Infertility and Reproductive Endocrinology, Poznań University of Medical Sciences, Poland. The study group consisted of 230 men who gave sperm samples for the first time in our center as part of an infertility investigation. The samples underwent manual and computer-assisted assessment of concentration, motility and morphology. A total of 184 samples were examined twice: manually, according to the 2010 WHO recommendations, and with CASA, using the program set-tings provided by the manufacturer. Additionally, 46 samples underwent two manual analyses and two computer-assisted analyses. The p-value of p CASA and manually. In the group of patients where all analyses with each method were performed twice on the same sample we found no significant differences between both assessments of the same probe, neither in the samples analyzed manually nor with CASA, although standard deviation was higher in the CASA group. Our results suggest that computer-assisted sperm analysis requires further improvement for a wider application in clinical practice.

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

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.

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

A Study on planning of promotion for international collaborative development of Generation IV Nuclear Energy Systems

International Nuclear Information System (INIS)

Hee, Chang Moon; Yang, M. S.; Ha, J. J.

2006-06-01

Korea has participated in the international collaboration programs for the development of future nuclear energy systems driven by the countries holding advanced nuclear technology and Korea and U. S. have cooperated in the INERI. This study is mainly at developing the plan for participation in the collaborative development of the Gen IV, searching the participation strategy for INERI and the INPRO, and the international cooperation in these programs. Contents and scope of the study for successful achievement are as follows; - Investigation and analysis of international and domestic trends related to advanced nuclear technologies - Development of the plan for collaborative development of the Gen IV and conducting the international cooperation activities - Support for the activities related to I-NERI between Korea and U. S. and conducting the international cooperation - International cooperation activities for the INPRO This study can be useful for planning the research plan and setting up of the strategy of integrating the results of the international collaboration and the domestic R and D results by combining the Gen IV and the domestic R and D in the field of future nuclear technology. Furthermore, this study can contribute to establishing the effective foundation and broadening the cooperation activities not only with the advanced countries for acquisition of the advanced technologies but also with the developing countries for the export of the domestic nuclear energy systems

Design/CPN. A Reference Manual

DEFF Research Database (Denmark)

Jensen et. al, Kurt

/CPN WWW pages. To speed up the access to the Design/CPN manuals we recommend to keep a local copy - which may be shared by all users in your organisation. In this way you do not need to go via our WWW server each time you need to look in a manual. For some of the largest manuals, we also supply files......Note: The manuals are available as PDF files . There are two sets of manuals - one for the Unix platform and another for the Mac platform. Each set of manual consists of: Tutorial (for the Design/CPN editor and simulator) Reference Manual (for the Design/CPN editor and simulator) Programmer......'s Manual (with Design/OA functions and Charts) Occurrence Graph Manual (integrated tutorial and reference manual) OE/OS Graph Manual (integrated tutorial and reference manual) Other Manuals (e.g. a short overview of CPN ML).   The Tutorial, Reference Manual and Programmer's Manual are made for Design...

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.

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.

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2006-01-01

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

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2005-02-25

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

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...

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

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)

Comparison of automated and manual shielding block fabrication

International Nuclear Information System (INIS)

Weeks, K.J.; Fraass, B.A.; McShan, D.L.; Hardybala, S.S.; Hargreaves, E.A.; Lichter, A.S.

1989-01-01

This work reports the results of a study comparing computer controlled and manual shielding block cutting. The general problems inherent in automated block cutting have been identified and minimized. A system whose accuracy is sufficient for clinical applications has been developed. The relative accuracy of our automated system versus experienced technician controlled cutting was investigated. In general, it is found that automated cutting is somewhat faster and more accurate than manual cutting for very large fields, but that the reverse is true for most smaller fields. The relative cost effectiveness of automated cutting is dependent on the percentage of computer designed blocks which are generated in the clinical setting. At the present time, the traditional manual method is still favored

NIF ICCS Test Controller for Automated and Manual Testing

International Nuclear Information System (INIS)

Zielinski, J S

2007-01-01

The National Ignition Facility (NIF) Integrated Computer Control System (ICCS) is a large (1.5 MSLOC), hierarchical, distributed system that controls all aspects of the NIF laser [1]. The ICCS team delivers software updates to the NIF facility throughout the year to support shot operations and commissioning activities. In 2006, there were 48 releases of ICCS: 29 full releases, 19 patches. To ensure the quality of each delivery, thousands of manual and automated tests are performed using the ICCS Test Controller test infrastructure. The TestController system provides test inventory management, test planning, automated test execution and manual test logging, release testing summaries and test results search, all through a web browser interface. Automated tests include command line based frameworks server tests and Graphical User Interface (GUI) based Java tests. Manual tests are presented as a checklist-style web form to be completed by the tester. The results of all tests, automated and manual, are kept in a common repository that provides data to dynamic status reports. As part of the 3-stage ICCS release testing strategy, the TestController system helps plan, evaluate and track the readiness of each release to the NIF facility

Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

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.

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.

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.

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.

Janus neodymium glass laser operations manual

International Nuclear Information System (INIS)

Auerbach, J.M.; Holmes, N.C.; Trainor, R.J.

1978-01-01

A manual, prepared to guide personnel in operating and maintaining the Janus glass laser system, is presented. System components are described in detail. Step-by-step procedures are presented for firing the laser and for performing routine maintenance and calibration procedures

Sustainable Nuclear Energy for the 21st Century

International Nuclear Information System (INIS)

2010-09-01

Concerns over energy resource availability, energy security and climate change suggest an important role for nuclear power in supplying sustainable energy in the 21st century. The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2000 by a resolution of the IAEA General Conference to help ensure that nuclear energy is available to contribute to meeting global energy needs of the 21st century in a sustainable manner. It is a mechanism for IAEA Member States that have joined the project as INPRO members to collaborate on topics of joint interest. By 2010, INPRO membership had grown to 30 countries and the European Commission. The results of INPRO's activities, however, are made available to all IAEA Member States

Develpment of quality assurance manual for fabrication of DUPIC fuel

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT.

Develpment of quality assurance manual for fabrication of DUPIC fuel

International Nuclear Information System (INIS)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT

Software Users Manual (SUM): Extended Testability Analysis (ETA) Tool

Science.gov (United States)

Maul, William A.; Fulton, Christopher E.

2011-01-01

This software user manual describes the implementation and use the Extended Testability Analysis (ETA) Tool. The ETA Tool is a software program that augments the analysis and reporting capabilities of a commercial-off-the-shelf (COTS) testability analysis software package called the Testability Engineering And Maintenance System (TEAMS) Designer. An initial diagnostic assessment is performed by the TEAMS Designer software using a qualitative, directed-graph model of the system being analyzed. The ETA Tool utilizes system design information captured within the diagnostic model and testability analysis output from the TEAMS Designer software to create a series of six reports for various system engineering needs. The ETA Tool allows the user to perform additional studies on the testability analysis results by determining the detection sensitivity to the loss of certain sensors or tests. The ETA Tool was developed to support design and development of the NASA Ares I Crew Launch Vehicle. The diagnostic analysis provided by the ETA Tool was proven to be valuable system engineering output that provided consistency in the verification of system engineering requirements. This software user manual provides a description of each output report generated by the ETA Tool. The manual also describes the example diagnostic model and supporting documentation - also provided with the ETA Tool software release package - that were used to generate the reports presented in the manual

Study of developing nuclear fabrication facility's integrated emergency response manual

International Nuclear Information System (INIS)

Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang; Min, Guem Young; Han, Ji Ah

2016-01-01

Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type

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

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.

Quality manual for Laboratories of the Nuclear Materials Characterization Division

International Nuclear Information System (INIS)

Sabato, S.F.

1991-05-01

This publication presents the first Quality Manual for the Laboratories at the Nuclear Materials Characterization Division. The Manual describes the laboratories, its organization structure, fields of activities, personnel records, equipments, maintenance and calibration. The main aspects concerning quality assurance in the analysis were discussed. The whole system of receiving, identifying and processing analysis of the samples is shown. Since there are many information to be contained in several subjects of the Quality Manual, there were produced separate documents that are cross referenced in the manual. (author)

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.

77 FR 19077 - Adoption of Updated EDGAR Filer Manual

Science.gov (United States)

2012-03-30

... practice, publication for notice and comment is not required under the Administrative Procedure Act (APA...-30008] Adoption of Updated EDGAR Filer Manual AGENCY: Securities and Exchange Commission. ACTION: Final... Electronic Data Gathering, Analysis, and Retrieval System (EDGAR) Filer Manual to reflect updates to the...

76 FR 73506 - Adoption of Updated EDGAR Filer Manual

Science.gov (United States)

2011-11-29

... practice, publication for notice and comment is not required under the Administrative Procedure Act (APA...-29868] Adoption of Updated EDGAR Filer Manual AGENCY: Securities and Exchange Commission. ACTION: Final... Electronic Data Gathering, Analysis, and Retrieval System (EDGAR) Filer Manual to reflect updates to the...

Fast matching of sensor data with manual observations.

Science.gov (United States)

Jit, Biswas; Maniyeri, Jayachandran; Louis, Shue; Philip, Yap Lin Kiat

2009-01-01

In systems and trials concerning wearable sensors and devices used for medical data collection, the validation of sensor data with respect to manual observations is very important. However, this is often problematic because of feigned behavior, errors in manual recording (misclassification), gaps in recording (missing readings), missed observations and timing mismatch between manual observations and sensor data due to a difference in time granularity. Using sleep activity pattern monitoring as an example we present a fast algorithm for matching sensor data with manual observations. Major components include a) signal analysis to classify states of sleep activity pattern, b) matching of states with Sleep Diary (SD) and c) automated detection of anomalies and reconciliation of mismatches between the SD and the sensor data.

Unraveling the Mechanisms of Manual Therapy: Modeling an Approach.

Science.gov (United States)

Bialosky, Joel E; Beneciuk, Jason M; Bishop, Mark D; Coronado, Rogelio A; Penza, Charles W; Simon, Corey B; George, Steven Z

2018-01-01

Synopsis Manual therapy interventions are popular among individual health care providers and their patients; however, systematic reviews do not strongly support their effectiveness. Small treatment effect sizes of manual therapy interventions may result from a "one-size-fits-all" approach to treatment. Mechanistic-based treatment approaches to manual therapy offer an intriguing alternative for identifying patients likely to respond to manual therapy. However, the current lack of knowledge of the mechanisms through which manual therapy interventions inhibit pain limits such an approach. The nature of manual therapy interventions further confounds such an approach, as the related mechanisms are likely a complex interaction of factors related to the patient, the provider, and the environment in which the intervention occurs. Therefore, a model to guide both study design and the interpretation of findings is necessary. We have previously proposed a model suggesting that the mechanical force from a manual therapy intervention results in systemic neurophysiological responses leading to pain inhibition. In this clinical commentary, we provide a narrative appraisal of the model and recommendations to advance the study of manual therapy mechanisms. J Orthop Sports Phys Ther 2018;48(1):8-18. doi:10.2519/jospt.2018.7476.

TRENDS: A flight test relational database user's guide and reference manual

Science.gov (United States)

Bondi, M. J.; Bjorkman, W. S.; Cross, J. L.

1994-01-01

This report is designed to be a user's guide and reference manual for users intending to access rotocraft test data via TRENDS, the relational database system which was developed as a tool for the aeronautical engineer with no programming background. This report has been written to assist novice and experienced TRENDS users. TRENDS is a complete system for retrieving, searching, and analyzing both numerical and narrative data, and for displaying time history and statistical data in graphical and numerical formats. This manual provides a 'guided tour' and a 'user's guide' for the new and intermediate-skilled users. Examples for the use of each menu item within TRENDS is provided in the Menu Reference section of the manual, including full coverage for TIMEHIST, one of the key tools. This manual is written around the XV-15 Tilt Rotor database, but does include an appendix on the UH-60 Blackhawk database. This user's guide and reference manual establishes a referrable source for the research community and augments NASA TM-101025, TRENDS: The Aeronautical Post-Test, Database Management System, Jan. 1990, written by the same authors.

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,…

FTMP (Fault Tolerant Multiprocessor) programmer's manual

Science.gov (United States)

Feather, F. E.; Liceaga, C. A.; Padilla, P. A.

1986-01-01

The Fault Tolerant Multiprocessor (FTMP) computer system was constructed using the Rockwell/Collins CAPS-6 processor. It is installed in the Avionics Integration Research Laboratory (AIRLAB) of NASA Langley Research Center. It is hosted by AIRLAB's System 10, a VAX 11/750, for the loading of programs and experimentation. The FTMP support software includes a cross compiler for a high level language called Automated Engineering Design (AED) System, an assembler for the CAPS-6 processor assembly language, and a linker. Access to this support software is through an automated remote access facility on the VAX which relieves the user of the burden of learning how to use the IBM 4381. This manual is a compilation of information about the FTMP support environment. It explains the FTMP software and support environment along many of the finer points of running programs on FTMP. This will be helpful to the researcher trying to run an experiment on FTMP and even to the person probing FTMP with fault injections. Much of the information in this manual can be found in other sources; we are only attempting to bring together the basic points in a single source. If the reader should need points clarified, there is a list of support documentation in the back of this manual.

Orientation manual for INIS and AGRIS (OMINAS)

International Nuclear Information System (INIS)

Binggeli, M.H.

1979-01-01

The manual is intended as a basic introduction to the computerized information systems, INIS (International Nuclear Information System) and AGRIS (International Information System for the Agricultural Sciences and Technology). Both systems contain information on already published literature, and include non-conventional literature (i.e. literature not available through normal commercial channels). Full bibliographic details and a subject classification are given. INIS, in addition, supplies descriptors, data-flagged where appropriate, and abstracts with every item of literature reported. The guiding principle followed by INIS and AGRIS is one of shared responsibility in development and operation. Both input is decentralized. The collection and preparation of documents relevant to the defined subject scopes are the responsibility of the country of publication. This decentralized input is transmitted to Vienna where centralized processing, merging and dispatching take place. The main output products are two printed journals, INIS Atomindex and AGRINDEX, and magnetic tape services. The manual is divided into four parts. The first is intended as a general introduction, and gives a bird's-eye view of the principles involved in the operation of the two systems. The second and third deal with INIS and AGRIS, respectively, and offer orientation in greater depth. The last part deals with the computer aspects of the system. The manual contains several appendices, a subject index and a list of basic references

International Project on Innovative Nuclear Reactors and Fuel Cycles: Introduction and Education and Training Activity

International Nuclear Information System (INIS)

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

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 with aim to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. INPRO seeks to bring together technology holders, users and newcomers to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, with a particular focus on sustainability and needs of developing countries. It is a mechanism for INPRO Members to collaborate on topics of joint interest. INPRO activities are undertaken in close cooperation with Member States in the following main areas: Global Scenarios, Innovations, Sustainability Assessment and Strategies, Policy and Dialogue. The paper presents short introduction in INPRO and specifically the distant Education and Training INPRO activity on important topics of nuclear energy sustainability to audiences in different Member States. These activities can support capacity building and national human resource development in the nuclear energy sector. The main benefit of such training courses and workshops is that it is not only targeted to students, but also to lecturers of technical and nuclear universities. Moreover, young professionals working at nuclear energy departments, electric utilities, energy ministries and R&D institutions can participate in such training and benefit from it. (authors)

TWG-FR Activity Report for the Period May 2011 – May 2012

International Nuclear Information System (INIS)

Monti, Stefano

2012-01-01

Recent Recommendations of the TWG-FR & implementation: ⇨ Increase the efforts to make more countries participating in its activities → Sweden became full member of TWG-FR this year. ⇨ Concentrate all research and technical activities related to FR under the TWG-FR umbrella. An efficient and effective interface between INPRO and TWG-FR should be established to avoid duplication/overlapping of activities → done. ⇨ Closer cooperation links should be established with FR-related activities implemented within the framework of other international programmes (e.g. GIF, INPRO, OECD/NEA, ESNII) → systematic collaboration with INPRO, interface with GIF, participation to NEA-TF on SFR, member of External Advisory Committee of some Euratom projects. ⇨ Continue to secure training and education in the field of Fast Neutron System Physics, Technology and Applications, and respective Schools/Seminars should be held on a regular basis → 4 events: 2 in 2011 and 2 in 2012 (Trieste, Bariloche). ⇨ Launch new CRPs in the field of safety of FR with special emphasis on severe accidents → launch of EBR-II CRP + 4 related Workshops/TMs. ⇨ The IAEA, with technical inputs from the TWG-FR, should produce international safety standards relevant to fast reactors → Initiated discussion with Department of Nuclear Safety and Security + INPRO/GIF for SFR Safety Design Criteria

Salinas. Theory Manual Version 2.8

Energy Technology Data Exchange (ETDEWEB)

Reese, Garth M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walsh, Timothy [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bhardwaj, Manoj K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2009-02-01

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, Users 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.

PC/FRAM, Version 3.2 User Manual

International Nuclear Information System (INIS)

Kelley, T.A.; Sampson, T.E.

1999-01-01

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descenies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S 'chn' and 'SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added in the future. Support for reading and writing CAM files will also be forthcoming. A versatile parameter fde database structure governs all facets of the data analysis. User editing of the parameter sets allows great flexibility in handling data with different isotopic distributions, interfering isotopes, and different acquisition parameters such as energy calibration, and detector type. This manual is intended for the system supervisor or the local user who is to be the resident expert. Excerpts from this manual may also be appropriate for the system operator who will routinely use the instrument

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

Wastes power generation introduction manual. Material edition; Haikibutsu hatsuden donyu manual. Shiryohen

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

This paper collects and puts into order the materials used in preparing the manual. The materials were classified into the power generation system database related to discussion of the economic performance, case studies, technical materials, other referential materials and glossary. The database shows power generation efficiency, auxiliary power ratio, construction cost, utility cost and number of operators. The case studies present examples of economy calculations on the five recommended power generation systems at a wastes treatment capacity of 180 tons a day. Technical materials put into order the technological discussions on efficiency improvement, environmental measures (suppression of discharge of dioxins, measures for their removal, and the effects thereof), refuse derived fuel (RDF) and power plant operating techniques. The other referential materials collect laws, notifications, and guidelines related to the Welfare Ministry, laws, notifications, criteria and related to the Ministry of International Trade and Industry, and materials related to LCA, forms of power generation business entities, general wastes disposal business, and electric business bonds. The glossary explains terms required for operation and understanding of the manual. (NEDO)

INTRA/Mod3.2. Manual and code description. Volume 2 - User's manual

International Nuclear Information System (INIS)

Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

1999-01-01

The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User's Manual is an input description. This document, the User's Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

78 FR 4766 - Adoption of Updated EDGAR Filer Manual

Science.gov (United States)

2013-01-23

..., publication for notice and comment is not required under the Administrative Procedure Act (APA).\\7\\ It follows...-68644; 39-2488; IC-30348] Adoption of Updated EDGAR Filer Manual AGENCY: Securities and Exchange...) Filer Manual and related rules to reflect updates to the EDGAR system. The revisions are being made...

47 CFR 1.1705 - Forms; electronic and manual filing.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Forms; electronic and manual filing. 1.1705... Operations and Licensing System (COALS) § 1.1705 Forms; electronic and manual filing. (a) Application forms... Cable Television Relay Service (CARS) shall use the following forms and associated schedules: (1) FCC...

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...

Ciencias 2. Manual do Professor (Science Teacher's Manual).

Science.gov (United States)

Raposo, Lucilia

This is the teacher's manual for Ciencias 2, the second in a series of elementary science textbooks for Portuguese-speaking students. The student textbook contains 10 chapters and 57 activities. The teacher's manual presents an explanation of the educational goals and the organization of the content, Topics included are environment, the human,…

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.

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

Egyptian Mythological Manuals

DEFF Research Database (Denmark)

Jørgensen, Jens Kristoffer Blach

From the hands of Greek mythographers a great number of myths have survived along with philosophical discussions of their meaning and relevance for the Greeks. It is little known that something similar existed in ancient Egypt where temple libraries and archives held scholarly literature used...... by the native priesthood, much of which has only been published in recent years. As part of this corpus of texts, the ancient Egyptian mythological manuals offer a unique perspective on how the Egyptian priesthood structured and interpreted Egyptian myths. The thesis looks at the different interpretative...... techniques used in the Tebtunis Mythological Manual (Second century CE) and the Mythological Manual of the Delta (Sixth century BCE) and the place of these manuals within the larger corpus of priestly scholarly literature from ancient Egypt. To organize the wealth of local myths the manuals use model...

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-02

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

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…

Supporting innovation. International Project on Innovative Nuclear Reactors and Fuel Cycles moves into first phase

International Nuclear Information System (INIS)

Gowin, Peter J.; Kupitz, Juergen

2001-01-01

energy needs and environmental impact. In order for nuclear energy 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, safety, waste and potential proliferation risks.' INPRO's objectives, as defined in the Terms of Reference, are: to help to ensure that nuclear energy is available to contribute in fulfilling, in a sustainable manner, energy needs in the 21st century; to bring together all interested Member States, 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 that use sound and economically competitive technology, are based - to the extent possible - on systems with inherent safety features and minimise the risk of proliferation and the impact on the environment; to create a process that involves all relevant stake holders 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. INPRO is an Agencywide project, with contributions from all relevant IAEA Departments within available resources. The Project will be implemented in two phases. Phase I was initiated in early 2001 and is planned to run to 2003. In the first phase, work will proceed in five subject areas recognized as important for the future development of nuclear energy technology, and on two parallel tracks. Upon successful completion of INPRO's first phase, taking into account advice from the Steering Committee, and with the approval of participating Member States, a second phase of INPRO may be initiated. Drawing on the results from the first phase, it would be directed at: examining in the context of available technologies the feasibility of commencing an international project; and identifying technologies which might be appropriate for

Dysfunctional Workers, Functional Texts: The Transformation of Work in Institutional Procedure Manuals.

Science.gov (United States)

Sullivan, Francis J.

1997-01-01

Examines how conflicts between management and workers over division of labor are enacted in two manuals--the official manual operationalizing Internal Revenue Service (IRS) regulations and a "translation" of the official manual--governing tax examiners' work in an IRS Service Center. Finds that systemic differences between the manuals…

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.

Sandia SWiFT Wind Turbine Manual.

Energy Technology Data Exchange (ETDEWEB)

White, Jonathan; LeBlanc, Bruce Philip; Berg, Jonathan Charles; Bryant, Joshua; Johnson, Wesley D.; Paquette, Joshua

2016-01-01

The Scaled Wind Farm Technology (SWiFT) facility, operated by Sandia National Laboratories for the U.S. Department of Energy's Wind and Water Power Program, is a wind energy research site with multiple wind turbines scaled for the experimental study of wake dynamics, advanced rotor development, turbine control, and advanced sensing for production-scale wind farms. The SWiFT site currently includes three variable-speed, pitch-regulated, three-bladed wind turbines. The six volumes of this manual provide a detailed description of the SWiFT wind turbines, including their operation and user interfaces, electrical and mechanical systems, assembly and commissioning procedures, and safety systems. Further dissemination only as authorized to U.S. Government agencies and their contractors; other requests shall be approved by the originating facility or higher DOE programmatic authority. 111 UNCLASSIFIED UNLIMITED RELEASE Sandia SWiFT Wind Turbine Manual (SAND2016-0746 ) approved by: Department Manager SWiFT Site Lead Dave Minster (6121) Date Jonathan White (6121) Date SWiFT Site Supervisor Dave Mitchell (6121) Date Note: Document revision logs are found after the title page of each volume of this manual. iv

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.

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

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

Estimator's electrical man-hour manual

CERN Document Server

Page, John S

1999-01-01

This manual's latest edition continues to be the best source available for making accurate, reliable man-hour estimates for electrical installation. This new edition is revised and expanded to include installation of electrical instrumentation, which is used in monitoring various process systems.

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

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.

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...

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-04-01

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

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2011-04-04

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

User requirements for innovative nuclear reactors and fuel cycle technologies in the area of economics, environment, safety, waste management, proliferation resistance and cross cutting issues, and methodology for innovative technologies assessment

International Nuclear Information System (INIS)

Kupitz, Juergen; Depisch, Frank; Allan, Colin

2003-01-01

The IAEA General Conference in 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''. In response to this invitation, the IAEA initiated an ''International Project on Innovative Nuclear Reactors and Fuel Cycles'', INPRO. The overall objectives of INPRO is to help to ensure that nuclear energy is available to contribute in fulfilling in a sustainable manner energy needs in the 21st century, and to bring together all interested Member States, 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 that use sound and economically competitive technology. Phase-I of INPRO was initiated in May 2001. During Phase-I, work was subdivided in two sub phase: Phase 1A (finished in June 2003) and Phase 1B (started in June 2003). Phase 1A dealt with the definition of Basic Principles, User Requirements and Criteria, and the development of a methodology for the evaluation of innovative nuclear technologies. In Phase 1A, task groups for several areas were established: (a) Prospects and Potentials of Nuclear Power, (b) Economics; (c) Sustainability and Environment, (d) Safety of Nuclear Installations, (e) Waste Management, (f) Proliferation Resistance, (g) Crosscutting issues and (h) for the Methodology for Assessment. In Phase-IB evaluations of innovative nuclear energy technologies will be performed by Member States against the INPRO Basic Principles, User Requirements and Criteria. This paper summarizes the results achieved in the Phase 1A of INPRO and is a cooperative effort of the INPRO team, consisting of all INPRO cost free experts and task managers. (author)

Architectural study of the design and operation of advanced force feedback manual controllers

Science.gov (United States)

Tesar, Delbert; Kim, Whee-Kuk

1990-01-01

A teleoperator system consists of a manual controller, control hardware/software, and a remote manipulator. It was employed in either hazardous or unstructured, and/or remote environments. In teleoperation, the main-in-the-loop is the central concept that brings human intelligence to the teleoperator system. When teleoperation involves contact with an uncertain environment, providing the feeling of telepresence to the human operator is one of desired characteristics of the teleoperator system. Unfortunately, most available manual controllers in bilateral or force-reflecting teleoperator systems can be characterized by their bulky size, high costs, or lack of smoothness and transparency, and elementary architectures. To investigate other alternatives, a force-reflecting, 3 degree of freedom (dof) spherical manual controller is designed, analyzed, and implemented as a test bed demonstration in this research effort. To achieve an improved level of design to meet criteria such as compactness, portability, and a somewhat enhanced force-reflecting capability, the demonstration manual controller employs high gear-ratio reducers. To reduce the effects of the inertia and friction on the system, various force control strategies are applied and their performance investigated. The spherical manual controller uses a parallel geometry to minimize inertial and gravitational effects on its primary task of transparent information transfer. As an alternative to the spherical 3-dof manual controller, a new conceptual (or parallel) spherical 3-dof module is introduced with a full kinematic analysis. Also, the resulting kinematic properties are compared to those of other typical spherical 3-dof systems. The conceptual design of a parallel 6-dof manual controller and its kinematic analysis is presented. This 6-dof manual controller is similar to the Stewart Platform with the actuators located on the base to minimize the dynamic effects. Finally, a combination of the new 3-dof and 6-dof

International project on innovative nuclear reactors and fuel cycles

International Nuclear Information System (INIS)

Mourogov, V. M.; Juhn, P. E.

2003-01-01

In response to two IAEA General Conference Resolutions in September 2000, the IAEA has launched the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) in May 2001. As of February 2003, 12 IAEA Member States and the European Commission have become members of INPRO. In total, 19 cost-free experts have been nominated by these Member States and the European Commission to work for the INPRO project at the IAEA. Four meetings of the INPRO Steering Committee (SC), which is the decision and review body of INPRO, were held, two in 2001 and another two in 2002. The objective of INPRO, which is composed of two phases (Phase 1 and Phase 2), is to support safe, economic and proliferation resistant use of nuclear technology, in a sustainable manner, to meet the global energy needs in the next 50 years and beyond. During Phase 1, work is also subdivided in two sub phases: The currently on-going Phase 1A is focussing on the selection of criteria and development of methodologies and guidelines for the comparison of different reactor and fuel cycle concepts and approaches, taking into account the compilation and review of such concepts and approaches, and determination of user requirements in the areas of economics; environment; safety; proliferation-resistance; and cross cutting issues. The preliminary results of Phase 1A with respect to user requirements are summarized in the paper

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2009-08-28

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

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...

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.

Spent nuclear fuel project cold vacuum drying facility operations manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

HERMES II experimenters' manual (revised)

International Nuclear Information System (INIS)

Schuch, R.L.

1977-04-01

The HERMES II is a high-intensity laboratory photon source for gamma-ray radiation effects experiments as well as a high-energy pulsed electron beam generator for a variety of potential applications. The purpose of this manual is to serve as a basic source of information for prospective users of HERMES. Included is a brief discussion of the design and operation of the accelerator system as well as a summary of environmental data for x-ray operation and output characteristics for electron beam modes. The manual also contains a description of the HERMES experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

Portable Digital Radiography and Computed Tomography Manual

Energy Technology Data Exchange (ETDEWEB)

2007-11-01

This user manual describes the function and use of the portable digital radiography and computed tomography (DRCT) scanner. The manual gives a general overview of x-ray imaging systems along with a description of the DRCT system. An inventory of the all the system components, organized by shipping container, is also included. In addition, detailed, step-by-step procedures are provided for all of the exercises necessary for a novice user to successfully collect digital radiographs and tomographic images of an object, including instructions on system assembly and detector calibration and system alignment. There is also a short section covering the limited system care and maintenance needs. Descriptions of the included software packages, the DRCT Digital Imager used for system operation, and the DRCT Image Processing Interface used for image viewing and tomographic data reconstruction are given in the appendixes. The appendixes also include a cheat sheet for more experienced users, a listing of known system problems and how to mitigate them, and an inventory check-off sheet suitable for copying and including with the machine for shipment purposes.

INTRA/Mod3.2. Manual and code description. Volume 2 - User`s manual

Energy Technology Data Exchange (ETDEWEB)

Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

1999-01-01

The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User`s Manual is an input description. This document, the User`s Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

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

Manual on mathematical models in isotope hydrogeology

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

Methodologies based on the use of naturally occurring isotopes are, at present, an integral part of studies being undertaken for water resources assessment and management. Quantitative evaluations based on the temporal and/or spatial distribution of different isotopic species in hydrological systems require conceptual mathematical formulations. Different types of model can be employed depending on the nature of the hydrological system under investigation, the amount and type of data available, and the required accuracy of the parameter to be estimated. This manual provides an overview of the basic concepts of existing modelling approaches, procedures for their application to different hydrological systems, their limitations and data requirements. Guidance in their practical applications, illustrative case studies and information on existing PC software are also included. While the subject matter of isotope transport modelling and improved quantitative evaluations through natural isotopes in water sciences is still at the development stage, this manual summarizes the methodologies available at present, to assist the practitioner in the proper use within the framework of ongoing isotope hydrological field studies. In view of the widespread use of isotope methods in groundwater hydrology, the methodologies covered in the manual are directed towards hydrogeological applications, although most of the conceptual formulations presented would generally be valid. Refs, figs, tabs.

Manual on mathematical models in isotope hydrogeology

International Nuclear Information System (INIS)

1996-10-01

Methodologies based on the use of naturally occurring isotopes are, at present, an integral part of studies being undertaken for water resources assessment and management. Quantitative evaluations based on the temporal and/or spatial distribution of different isotopic species in hydrological systems require conceptual mathematical formulations. Different types of model can be employed depending on the nature of the hydrological system under investigation, the amount and type of data available, and the required accuracy of the parameter to be estimated. This manual provides an overview of the basic concepts of existing modelling approaches, procedures for their application to different hydrological systems, their limitations and data requirements. Guidance in their practical applications, illustrative case studies and information on existing PC software are also included. While the subject matter of isotope transport modelling and improved quantitative evaluations through natural isotopes in water sciences is still at the development stage, this manual summarizes the methodologies available at present, to assist the practitioner in the proper use within the framework of ongoing isotope hydrological field studies. In view of the widespread use of isotope methods in groundwater hydrology, the methodologies covered in the manual are directed towards hydrogeological applications, although most of the conceptual formulations presented would generally be valid. Refs, figs, tabs

Camp Health Aide Manual = Manual para trabajadores de salud.

Science.gov (United States)

Robinson, June Grube; And Others

This bilingual manual serves as a textbook for migrant Camp Health Aides. Camp Health Aides are members of migrant labor camps enlisted to provide information about health and social services to migrant workers and their families. The manual is divided into 12 tabbed sections representing lessons. Teaching notes printed on contrasting paper…

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

The comparison of automated urine analyzers with manual microscopic examination for urinalysis automated urine analyzers and manual urinalysis.

Science.gov (United States)

İnce, Fatma Demet; Ellidağ, Hamit Yaşar; Koseoğlu, Mehmet; Şimşek, Neşe; Yalçın, Hülya; Zengin, Mustafa Osman

2016-08-01

Urinalysis is one of the most commonly performed tests in the clinical laboratory. However, manual microscopic sediment examination is labor-intensive, time-consuming, and lacks standardization in high-volume laboratories. In this study, the concordance of analyses between manual microscopic examination and two different automatic urine sediment analyzers has been evaluated. 209 urine samples were analyzed by the Iris iQ200 ELITE (İris Diagnostics, USA), Dirui FUS-200 (DIRUI Industrial Co., China) automatic urine sediment analyzers and by manual microscopic examination. The degree of concordance (Kappa coefficient) and the rates within the same grading were evaluated. For erythrocytes, leukocytes, epithelial cells, bacteria, crystals and yeasts, the degree of concordance between the two instruments was better than the degree of concordance between the manual microscopic method and the individual devices. There was no concordance between all methods for casts. The results from the automated analyzers for erythrocytes, leukocytes and epithelial cells were similar to the result of microscopic examination. However, in order to avoid any error or uncertainty, some images (particularly: dysmorphic cells, bacteria, yeasts, casts and crystals) have to be analyzed by manual microscopic examination by trained staff. Therefore, the software programs which are used in automatic urine sediment analysers need further development to recognize urinary shaped elements more accurately. Automated systems are important in terms of time saving and standardization.

The Relationship between Manual Ability and Ambulation in Adolescents with Cerebral Palsy

Science.gov (United States)

Majnemer, Annette; Shikako-Thomas, Keiko; Shevell, Michael; Poulin, Chantal; Lach, Lucyna; Law, Mary; Schmitz, Norbert

2013-01-01

This study examined the relationship between gross motor function and manual ability in 120 adolescents with cerebral palsy (CP) (15.2, SD 2.1 years, 59.8% male). Adolescents were evaluated using the Gross Motor Function Classification System (GMFCS) and the Manual Ability Classification System (MACS). A neurologist classified CP subtype. Most…

Radiation protection technician job task analysis manual

International Nuclear Information System (INIS)

1990-03-01

This manual was developed to assist all DOE contractors in the design and conduct of job task analysis (JTA) for the radiation protection technician. Experience throughout the nuclear industry and the DOE system has indicated that the quality and efficiency in conducting a JTA at most sites is greatly enhanced by using a generic task list for the position, and clearly written guidelines on the JTA process. This manual is designed to provide this information for personnel to use in developing and conducting site-specific JTAs. (VC)

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

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…

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,…

National Best Practices Manual for Building High Performance Schools (Revised)

Energy Technology Data Exchange (ETDEWEB)

2007-10-01

The Best Practices Manual was written as a part of the promotional effort for EnergySmart Schools, provided by the US Department of Energy, to educate school districts around the country about energy efficiency and renewable energy. Written specifically for architects and engineers, The Best Practices Manual is designed to help those who are responsible for designing or retrofitting schools, as well as their project managers. This manual will help design staff make informed decisions about energy and environmental issues important to the school systems and communities.

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.

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.

Manual for environmental radiological surveillance

International Nuclear Information System (INIS)

Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

2010-03-01

Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

AIMSsim Version 2.3.4 - User Manual

National Research Council Canada - National Science Library

Schoenborn, Oliver; Lachance, Patrick; Bahramifarid, Nima

2008-01-01

This user manual provides an overview of the software functionality developed to support the empirical investigation of a simulated user interface for an Advanced Integrated Multi-sensor Surveillance (AIMS) system...

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...

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

Operating Manual of Helium Refrigerator (Rev. 2)

Energy Technology Data Exchange (ETDEWEB)

Song, K.M.; Son, S.H.; Kim, K.S.; Lee, S.K.; Kim, M.S. [Korea Electric Power Research Institute, Taejon (Korea)

2002-07-01

A helium refrigerator was installed as a supplier of 20K cold helium to the cryogenic distillation system of WTRF pilot plant. The operating procedures of the helium refrigerator, helium compressor and auxiliary apparatus are described for the safety and efficient operation in this manual. The function of the helium refrigerator is to remove the impurities from the compressed helium of about 250psig, to cool down the helium from ambient temperature to 20K through the heat exchanger and expansion engine and to transfer the cold helium to the cryogenic distillation system. For the smoothly operation of helium refrigerator, the preparation, the start-up, the cool-down and the shut-down of the helium refrigerator are described in this operating manual. (author). 3 refs., 14 tabs.

Postural adjustments are modulated by manual task complexity

Directory of Open Access Journals (Sweden)

Luis Augusto Teixeira

2009-09-01

Full Text Available Daily life activities of humans are characterized by dual tasks, in which a manual task is performed concomitantly with a postural task. Based on the assumption that both manual and postural tasks require attentional resources, no consensus exists as to how the central nervous system modulates postural adjustments in dual tasks. The aim of the present study was to analyze the effect of a manual task requiring attentional resources on shoulder and ankle adjustments as a function of the direction and predictability of postural perturbation. The participants (n=6 were evaluated during the performance of a simple and a complex manual task, while the base of support was moved backward or forward. Latency of activation of the tibialis anterior and gastroc-nemius muscles and angular acceleration of the shoulder were analyzed. The results showed that execution of the complex manual task delayed postural adjustment. Moreover, this delay occurred differently depending on the direction of postural perturbation. The delay in postural adjustment occurred proximally in the case of anterior displacement of the platform, and distally in the case of posterior displacement. Postural adjustments were more affected by the attentional task than by the predictability of platform displacement. These results are consistent with the concept of an integrated control between manual actions and the maintenance of static posture.

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.

SHARP User Manual

Energy Technology Data Exchange (ETDEWEB)

Yu, Y. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, E. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Thomas, J. W. [Argonne National Lab. (ANL), Argonne, IL (United States); Mahadevan, Vijay S. [Argonne National Lab. (ANL), Argonne, IL (United States); Rahaman, Ronald O. [Argonne National Lab. (ANL), Argonne, IL (United States); Solberg, Jerome [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-03-31

SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

SHARP User Manual

International Nuclear Information System (INIS)

Yu, Y. Q.; Shemon, E. R.; Thomas, J. W.; Mahadevan, Vijay S.; Rahaman, Ronald O.; Solberg, Jerome

2016-01-01

SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

Sensitometric characteristics of D-, E- and F-speed dental radiographic films in manual and automatic processing

Directory of Open Access Journals (Sweden)

Jahangir Haghani

2012-12-01

Full Text Available BACKGROUND: The purpose of this study was to evaluate the sensitometric characteristics of Ultraspeed, Ektaspeed Plus and Insight dental radiographic films using manual and automatic processing systems. METHODS: In this experimental invitro study, an aluminum step-wedge was used to construct characteristic curves for D-, E- and F-speed radiographic films (Kodak Eastman, Rochester, USA. All films were processed in Iranian processing solution (chemical industries Co., Iran, Tehran both manually and automatically in a period of six days. Unexposed films of three types were processed manually and automatically to determine base plus fog density. Speed and film contrast were measured according to International Standard Organization definition. RESULTS: There was significant difference in density obtained with the D-, E- and F-speed films in both manually and automatically processing systems (P < 0.001. There was significant difference in density obtained with the Ultraspeed and insight films. There was no significant difference in contrast obtained with the D-, E- and F-speed films in both manually and automatically processing systems (P = 0.255 , P = 0.26. There was significant difference in speed obtained with the D-, E- and F-speed films in both manually and automatically processing systems (P = 0.034, P = 0.04. CONCLUSIONS: The choice of processing system can affect radiographic characteristics. The F-speed film processed in automatic system has greater speed in comparison with manual processing system, and it provides a further reduction in radiation exposure without detriment to image quality.

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.

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)

AIMSsim Version 2.2.1, User Manual

National Research Council Canada - National Science Library

Schoenborn, Oliver

2007-01-01

This user manual provides an overview of how to use the software developed to support the empirical investigation of a simulated user interface for an Advanced Integrated Multi sensor Surveillance (AIMS) system...

Fuel Element Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Burley, H.H. [ed.

1956-08-01

It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.

The comparison of automated urine analyzers with manual microscopic examination for urinalysis automated urine analyzers and manual urinalysis

Directory of Open Access Journals (Sweden)

Fatma Demet Ä°nce

2016-08-01

Full Text Available Objectives: Urinalysis is one of the most commonly performed tests in the clinical laboratory. However, manual microscopic sediment examination is labor-intensive, time-consuming, and lacks standardization in high-volume laboratories. In this study, the concordance of analyses between manual microscopic examination and two different automatic urine sediment analyzers has been evaluated. Design and methods: 209 urine samples were analyzed by the Iris iQ200 ELITE (Ä°ris Diagnostics, USA, Dirui FUS-200 (DIRUI Industrial Co., China automatic urine sediment analyzers and by manual microscopic examination. The degree of concordance (Kappa coefficient and the rates within the same grading were evaluated. Results: For erythrocytes, leukocytes, epithelial cells, bacteria, crystals and yeasts, the degree of concordance between the two instruments was better than the degree of concordance between the manual microscopic method and the individual devices. There was no concordance between all methods for casts. Conclusion: The results from the automated analyzers for erythrocytes, leukocytes and epithelial cells were similar to the result of microscopic examination. However, in order to avoid any error or uncertainty, some images (particularly: dysmorphic cells, bacteria, yeasts, casts and crystals have to be analyzed by manual microscopic examination by trained staff. Therefore, the software programs which are used in automatic urine sediment analysers need further development to recognize urinary shaped elements more accurately. Automated systems are important in terms of time saving and standardization. Keywords: Urinalysis, Autoanalysis, Microscopy

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.

MARS CODE MANUAL VOLUME V: Models and Correlations

International Nuclear Information System (INIS)

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

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 models and correlations manual provides a complete list of detailed information of the thermal-hydraulic models used in MARS, so that 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

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.

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

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.

Computerized operation manual (COM) of nuclear power plants

International Nuclear Information System (INIS)

Szegi, Z.

1985-01-01

This paper is to be presented at the International Seminar on Diagnoses of and Response to Abnormal Occurrences at Nuclear Power Plants organized by the International Atomic Energy Agency. The topic of presentation is the Computerized Operational Manual. This system supports the operator at disturbance situations by displaying quickly and unambiguously the operational instructions and the relevant information without mistakes. By the computerized manual the operator can determine the instruction-subsystem which reflects the real state of the power unit. From this point the system guides the operator on how to drive the unit to another determined state by providing the operational instructions at any time. A data bank is also included which contains information concerning rules restricting on maintenance and repair. The system will be realized at Paks NPP. (author)

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…

Radiological control manual. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

Radiological control manual. Revision 1

International Nuclear Information System (INIS)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP

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)

Elevated-temperature (6000F), manual contact ultrasonic examination

International Nuclear Information System (INIS)

Donnelly, C.W.

1981-01-01

Manual contact ultrasonic examination at temperatures above 250 0 F has not been successful in providing meaningful results. Sensitivity of standard transducers degrades rapidly at 250 0 F and above. It has been demonstrated that by using standard transducers and commercially available wedges and couplants in combination with a couplant/cooler system, manual contact ultrasonic examination can be performed at 600 0 F for an essentially 100% duty cycle in conformance to the sensitivity requirement of the ASME B and PV Code

Study of developing nuclear fabrication facility's integrated emergency response manual

Energy Technology Data Exchange (ETDEWEB)

Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang [KEPCO, Daejeon (Korea, Republic of); Min, Guem Young; Han, Ji Ah [Dongguk Univ., Daejeon (Korea, Republic of)

2016-05-15

Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type.

Salinas : theory manual.

Energy Technology Data Exchange (ETDEWEB)

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

2004-08-01

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 programer-notes manual, the user's notes and of course the material in the open literature.

Technical Manual for the SAM Biomass Power Generation Model

Energy Technology Data Exchange (ETDEWEB)

Jorgenson, J.; Gilman, P.; Dobos, A.

2011-09-01

This technical manual provides context for the implementation of the biomass electric power generation performance model in the National Renewable Energy Laboratory's (NREL's) System Advisor Model (SAM). Additionally, the report details the engineering and scientific principles behind the underlying calculations in the model. The framework established in this manual is designed to give users a complete understanding of behind-the-scenes calculations and the results generated.

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

WYLBUR reference manual. [For interactive text editing

Energy Technology Data Exchange (ETDEWEB)

Krupp, R.F.; Messina, P.C.; Peavler, J.M.; Schustack, S.; Starai, T.

1977-04-01

WYLBUR is a system for manipulating various kinds of text, such as computer programs, manuscripts, letters, forms, articles, or reports. Its on-line interactive text-editing capabilities allow the user to create, change, and correct text, and to search and display it. WYLBUR also has facilities for job submission and retrieval from remote terminals that make it possible for a user to inquire about the status of any job in the system, cancel jobs that are executing or awaiting execution, reroute output, raise job priority, or get information on the backlog of batch jobs. WYLBUR also has excellent recovery capabilities and a fast response time. This manual describes the WYLBUR version currently used at ANL. It is intended primarily as a reference manual; thus, examples of WYLBUR commands are kept to a minimum. (RWR)

Battery Test Manual For 48 Volt Mild Hybrid Electric Vehicles

Energy Technology Data Exchange (ETDEWEB)

Walker, Lee Kenneth [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-03-01

This manual details the U.S. Advanced Battery Consortium and U.S. Department of Energy Vehicle Technologies Program goals, test methods, and analysis techniques for a 48 Volt Mild Hybrid Electric Vehicle system. The test methods are outlined stating with characterization tests, followed by life tests. The final section details standardized analysis techniques for 48 V systems that allow for the comparison of different programs that use this manual. An example test plan is included, along with guidance to filling in gap table numbers.

Battery Test Manual For 48 Volt Mild Hybrid Electric Vehicles

International Nuclear Information System (INIS)

Walker, Lee Kenneth

2017-01-01

This manual details the U.S. Advanced Battery Consortium and U.S. Department of Energy Vehicle Technologies Program goals, test methods, and analysis techniques for a 48 Volt Mild Hybrid Electric Vehicle system. The test methods are outlined stating with characterization tests, followed by life tests. The final section details standardized analysis techniques for 48 V systems that allow for the comparison of different programs that use this manual. An example test plan is included, along with guidance to filling in gap table numbers.

Mars 2.2 code manual: input requirements

International Nuclear Information System (INIS)

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

2003-07-01

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 input manual provides a complete list of input required to run MARS. The manual is divided largely into two parts, namely, the one-dimensional part and the multi-dimensional part. The inputs for auxiliary parts such as minor edit requests and graph formatting inputs are shared by the two parts and as such mixed input is possible. The overall structure of the input 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 MARS. MARS development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

MARS code manual volume II: input requirements

International Nuclear Information System (INIS)

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

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 input manual provides a complete list of input required to run MARS. The manual is divided largely into two parts, namely, the one-dimensional part and the multi-dimensional part. The inputs for auxiliary parts such as minor edit requests and graph formatting inputs are shared by the two parts and as such mixed input is possible. The overall structure of the input 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

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

Manual method for dose calculation in gynecologic brachytherapy; Metodo manual para o calculo de doses em braquiterapia ginecologica

Energy Technology Data Exchange (ETDEWEB)

Vianello, Elizabeth A.; Almeida, Carlos E. de [Instituto Nacional do Cancer, Rio de Janeiro, RJ (Brazil); Biaggio, Maria F. de [Universidade do Estado, Rio de Janeiro, RJ (Brazil)

1998-09-01

This paper describes a manual method for dose calculation in brachytherapy of gynecological tumors, which allows the calculation of the doses at any plane or point of clinical interest. This method uses basic principles of vectorial algebra and the simulating orthogonal films taken from the patient with the applicators and dummy sources in place. The results obtained with method were compared with the values calculated with the values calculated with the treatment planning system model Theraplan and the agreement was better than 5% in most cases. The critical points associated with the final accuracy of the proposed method is related to the quality of the image and the appropriate selection of the magnification factors. This method is strongly recommended to the radiation oncology centers where are no treatment planning systems available and the dose calculations are manually done. (author) 10 refs., 5 figs.

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

Camellia v1.0 Manual: Part I

Energy Technology Data Exchange (ETDEWEB)

Roberts, Nathan V. [Argonne National Lab. (ANL), Argonne, IL (United States). Argonne Leadership Computing Facility

2016-09-28

Camellia began as an effort to simplify implementation of efficient solvers for the discontinuous Petrov-Galerkin (DPG) finite element methodology of Demkowicz and Gopalakrishnan. Since then, the feature set has expanded, to allow implementation of traditional continuous Galerkin methods, as well as discontinuous Galerkin (DG) methods, hybridizable DG (HDG) methods, first-order-system least squares (FOSLS), and the primal DPG method. This manual serves as an introduction to using Camellia. We begin, in Section 1.1, by describing some of the core features of Camellia. In Section 1.2 we provide an outline of the manual as a whole.

Manual on quality assurance programme auditing

International Nuclear Information System (INIS)

1984-01-01

The objective of this Manual is to provide guidance and illustrative examples of the methodology and techniques of internal and external audits that are consistent with the requirements and recommendations of the Code and the Safety Guide. The methodology and techniques are based on the practices of Member States having considerable experience in auditing QA programmes. This Manual is directed primarily towards QA programme auditors and managers and presents methods and techniques considered appropriate for the preparation and performance of audits and the evaluation of results. Its scope includes the techniques and methods used to carry out QA programme audits variously described as 'System', 'Product' and 'Process' audits. The techniques and methods described here may be used as one approach to the evaluation of suppliers' QA capabilities as defined in 50-SG-QA10. Although the Manual is primarily directed towards purchasers and suppliers, it is also relevant to regulatory organizations, such as government offices responsible for quality assurance, which carry out external audits independent of purchasers and suppliers. In such cases similar methods, procedures and techniques may be used

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.

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

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.

Technical Manual: easyCBM. Technical Report #1408

Science.gov (United States)

Anderson, Daniel; Alonzo, Julie; Tindal, Gerald; Farley, Dan; Irvin, P. Shawn; Lai, Cheng-Fei; Saven, Jessica L.; Wray, Kraig A.

2014-01-01

Since the easyCBM© learning system was first published in 2006, over $8 million of federal funding (both from the Office of Special Education Programs and more recently from the Institute of Education Sciences) has been used to develop, study, and refine the assessments available on the system. This Technical Manual summarizes the ongoing research…

49 CFR 236.919 - Operations and Maintenance Manual.

Science.gov (United States)

2010-10-01

..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Standards for Processor-Based Signal and Train Control Systems § 236.919 Operations and Maintenance Manual. (a... identify all software versions, revisions, and revision dates. Plans must be legible and correct. (c...

49 CFR 236.1039 - Operations and Maintenance Manual.

Science.gov (United States)

2010-10-01

..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Positive Train Control Systems § 236.1039 Operations and Maintenance Manual. (a) The railroad shall catalog and... software versions, revisions, and revision dates. Plans must be legible and correct. (c) Hardware, software...

GO methodology. Volume 1. Overview manual

International Nuclear Information System (INIS)

1983-06-01

The GO methodology is a success-oriented probabilistic system performance analysis technique. The methodology can be used to quantify system reliability and availability, identify and rank critical components and the contributors to system failure, construct event trees, and perform statistical uncertainty analysis. Additional capabilities of the method currently under development will enhance its use in evaluating the effects of external events and common cause failures on system performance. This Overview Manual provides a description of the GO Methodology, how it can be used, and benefits of using it in the analysis of complex systems

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.

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....

Universal Fast Breeder Reactor Subassembly Counter manual

International Nuclear Information System (INIS)

Menlove, H.O.; Eccleston, G.W.; Swansen, J.E.; Goris, P.; Abedin-Zadeh, R.; Ramalho, A.

1984-08-01

A neutron coincidence counter has been designed for the measurement of fast breeder reactor fuel assemblies. This assay system can accommodate the full range of geometries and masses found in fast breeder subassemblies under IAEA safeguards. The system's high-performance capability accommodates high plutonium loadings of up to 16 kg. This manual describes the system and its operation and gives performance and calibration parameters for typical applications

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

Interlibrary Loan Communications Subsystem: Users Manual.

Science.gov (United States)

OCLC Online Computer Library Center, Inc., Dublin, OH.

The OCLC Interlibrary Loan (ILL) Communications Subsystem provides participating libraries with on-line control of ILL transactions. This user manual includes a glossary of terms related to the procedures in using the system. Sections describe computer entry, searching, loan request form, loan response form, ILL procedures, the special message…

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.

FINAS. Example manual. 2

International Nuclear Information System (INIS)

Iwata, Koji; Tsukimori, Kazuyuki; Ueno, Mutsuo

2003-12-01

FINAS is a general purpose structural analysis computer program which was developed by Japan Nuclear Cycle Development Institute for the analysis of static, dynamic and thermal responses of elastic and inelastic structures by the finite element method. This manual contains typical analysis examples that illustrate applications of FINAS to a variety of structural engineering problems. The first part of this manual presents fundamental examples in which numerical solutions by FINAS are compared with some analytical reference solutions, and the second part of this manual presents more complex examples intended for practical application. All the input data images and principal results for each problem are included in this manual for beginners' convenience. All the analyses are performed by using the FINAS Version 13.0. (author)

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2007-01-01

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

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2007-03-12

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

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.

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...

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

Dounreay Shuffler diagnostic software operations manual

International Nuclear Information System (INIS)

Eccleston, G.W.; Stuewe, B.; Klosterbuer, S.; Van Lyssel, T.

1985-07-01

This operations manual describes the test software for the Dounreay Shuffler. The Shuffler is an assay system, controlled by a Commodore PET computer, that measures the plutonium content in leached hulls at the fuel reprocessing plant in Dounreay, Scotland. The Shuffler contains a 252 Cf neutron source that is moved between storage and irradiation locations to obtain measurement data. A stepping motor control (SMC) module operates the Shuffler and accepts commands from the PET to move the source. This manual briefly describes the Shuffler and provides details on running and using the diagnostic software program. The communications protocol for message transmittal between the PET and SMC is defined and a detailed example of message sending is presented in an appendix

Inspector's manual for mechanically stabilized earth walls.

Science.gov (United States)

2010-06-01

The scope of the project is to develop a condition rating system, creation of an inspector's manual to reference during : inspection or address any training for inspectors at the district level. The research project will develop a MSE wall : conditio...

Universal Fast Breeder Reactor Subassembly Counter manual

Energy Technology Data Exchange (ETDEWEB)

Menlove, H.O.; Eccleston, G.W.; Swansen, J.E.; Goris, P.; Abedin-Zadeh, R.; Ramalho, A.

1984-08-01

A neutron coincidence counter has been designed for the measurement of fast breeder reactor fuel assemblies. This assay system can accommodate the full range of geometries and masses found in fast breeder subassemblies under IAEA safeguards. The system's high-performance capability accommodates high plutonium loadings of up to 16 kg. This manual describes the system and its operation and gives performance and calibration parameters for typical applications.

ACT Plan: Technical Manual. 2013/2014

Science.gov (United States)

ACT, Inc., 2013

2013-01-01

This manual contains information about the American College Test (ACT) Plan® program. The principal focus of this manual is to document the Plan program's technical adequacy in light of its intended purposes. This manual supersedes the 2011 edition. The content of this manual responds to requirements of the testing industry as established in the…

Design and installation manual for thermal energy storage

Energy Technology Data Exchange (ETDEWEB)

Cole, R L; Nield, K J; Rohde, R R; Wolosewicz, R M [eds.

1979-02-01

The purpose for this manual is to provide information on the design and installation of thermal energy storage in solar heating systems. It is intended for contractors, installers, solar system designers, engineers, architects, and manufacturers who intend to enter the solar energy business. The reader should have general knowledge of how solar heating systems operate and knowledge of construction methods and building codes. Knowledge of solar analysis methods such as f-chart, SOLCOST, DOE-1, or TRNSYS would be helpful. The information contained in the manual includes sizing storage, choosing a location for the storage device, and insulation requirements. Both air-based and liquid-based systems are covered with topics on designing rock beds, tank types, pump and fan selection, installation, costs, and operation and maintenance. Topics relevant to heating domestic water include safety, single- and dual-tank systems, domestic water heating with air- and liquid-based space heating system, and stand-alone domestic hot water systems. Several appendices present common problems with storage systems and their solutions, heat transfer fluid properties, heat exchanger sizing, and sample specifications for heat exchangers, wooden rock bins, steel tanks, concrete tanks, and fiberglass-reinforced plastic tanks.

Nuclear Future is Ten Years Old. Innovative Nuclear Technology Celebrates Anniversary at General Conference

International Nuclear Information System (INIS)

Verlini, Giovanni

2011-01-01

IAEA-led International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) marked today its tenth anniversary with a ceremony held on the opening day of the IAEA's annual General Conference. INPRO was established in 2000 to ensure that sustainable nuclear energy is available to meet the energy needs of the twenty-first century.

Polarized proton Target-III operators manual, revision A

International Nuclear Information System (INIS)

Hill, D.; Moretti, A.; Onesto, F.; Rynes, P.

1976-04-01

A revision is given of a manual containing standard operating procedures for the vacuum, cryogenic, and electronic systems of a polarized proton target. The discussion includes the target cryostat, the 3 He and 4 He pumping systems, remote monitors and controls, the microwave system, the magnet and power supply, the computerized polarization monitor, the 4 He liquifier and gas recovery system, and miscellaneous auxiliary equipment

Rad Chem data acquisition chassis users manual

International Nuclear Information System (INIS)

Jones, B.A.

1980-01-01

The Shiva Laser at LLL requires many forms of diagnostics to measure and analyze fusion experiments. This manual describes the operation of a Micro-Processor controlled data acquisition system designed at LLL to measure Neutron Activation during fusion experiments on the Shiva Laser

TADS Needs Assessment Procedures Manual, Summer 1980.

Science.gov (United States)

Black, Talbot; And Others

The TADS (Technical Assistance Development System) Needs Assessment Manual is designed to guide the comprehensive review of Handicapped Children's Early Education Program (HCEEP) demonstration projects in identifying technical assistance needs. An introduction reviews the TADS technical assistance model which includes program planning, needs…

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.

EML procedures manual

International Nuclear Information System (INIS)

Volchok, H.L.; de Planque, G.

1982-01-01

This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications

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)

Partners Plus: Families and Caregivers in Partnerships. A Family-Centered Guide to Respite Care. Trainer's Workshop Manual [and] Community Planning Manual [and] A Family Manual [and] Caregiver Manual.

Science.gov (United States)

Ownby, Lisa L.; Hooke, Amanda C.; Moore, Dee Wylie; Garland, Corinne W.; Frank, Adrienne

Four manuals on implementing the Partners Respite Model, which provides respite care for children with disabilities or chronic illnesses, comprise this document. The Community Planning Manual offers a step-by-step guide to replication of the Partners Respite Model and is divided into sections on developing the Partners program, implementing the…

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

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

2000-02-03

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

National Radiobiology Archives Distributed Access User's Manual, Version 1. 1

Energy Technology Data Exchange (ETDEWEB)

Smith, S.K.; Prather, J.C.; Ligotke, E.K.; Watson, C.R.

1992-06-01

This supplement to the NRA Distributed Access User's manual (PNL-7877), November 1991, describes installation and use of Version 1.1 of the software package; this is not a replacement of the previous manual. Version 1.1 of the NRA Distributed Access Package is a maintenance release. It eliminates several bugs, and includes a few new features which are described in this manual. Although the appearance of some menu screens has changed, we are confident that the Version 1.0 User's Manual will provide an adequate introduction to the system. Users who are unfamiliar with Version 1.0 may wish to experiment with that version before moving on to Version 1.1.

The ISIS Open GENIE user manual

International Nuclear Information System (INIS)

Akeroyd, F.A.; Ashworth, R.L.; Campbell, S.I.; Johnston, S.D.; Martin, J.M.; Moreton-Smith, C.M.; Sivia, D.S.

2000-01-01

This manual should enable you to become familiar with Open GENIE quickly and easily. It therefore complements the Open GENIE Reference Manual which should be used to understand the full meaning of Open GENIE commands. The reference manual is accessible on the ISIS web server at: http://www.isis.rl.ac.uk/GENIEReferenceManual/ and the user manual is planned to be accessible by January '98 at http://www.isis.rl.ac.ukIGENIEUserManual/. The Open GENIE User Manual is separated into two parts: Part A. The User Manual. An introduction to the use of Open GENIE. Part B. The Installation Guide. General information on how to install and run Open GENIE. Assuming that you are new to Open GENIE and have just downloaded a copy you will need to consult the Installation Guide to get Open GENIE installed on your machine. After this we recommend you experiment with some of the example files to get an idea of the capabilities of Open GENIE. For further information, comments, additions of routines that you feel should be included, please contact us at genie at isise.rl.ac.uk

Regulatory manual for staging of cancer by CT

International Nuclear Information System (INIS)

Solorzano Marin, Jose Reinaldo

2008-01-01

The exact level for staging and making decisions about therapy that will be applied to cancer patients at the Servicio de Radiologia e Imagenes Medicas has been important for the Hospital Calderon Guardia. A template of report or manual has been suggested, with the information necessary for staging a particular type of cancer by analyzing the tomography of the patient. The TNM International System has been used to design the template of report, with a specific technical language and terminology unified theme for the oncologist and radiologist. This system is abstracted in the sixth edition of oncological staging manual of the American Joint Committee and its atlas; resources already acquired, and the helical CT scanner. The experience of the radiologist is critical, because he will be responsible to fill the document. [es

The operation and maintenance manual

International Nuclear Information System (INIS)

Stoll, A.; Krotil, H.; Klein, W.

1976-01-01

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. The operating manual is an essential element in bringing man and machine in harmony. This is necessary for safe and, as far as possible, uninterrupted operation of the power plant. The operating manual is the only document containing binding instructions for plant operation. All the tasks of plant operation which are carried out by plant staff are described in the operating manual in a form which is as clear and comprehensible as possible. A considerable number of these tasks can only be carried out by man, namely: 1) tasks concerning operational organization, 2) all non-automated areas of plant operation. (orig./TK) [de

Fire Protection Program Manual

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2012-05-18

This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

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

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

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

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

User's manual about visualizing debugger, vdebug

International Nuclear Information System (INIS)

Matsuda, Katsuyuki; Takemiya, Hiroshi; Kawasaki, Takuji

1998-12-01

We developed a visualizing debugger, vdebug, which works in cooperation with the visualization system AVS and source level debuggers (gdb, dbx, and ladebug), whereby we can visualize any array data without recompiling, and find errors in programs efficiently. This report is user's manual about a visualizing debugger, vdebug, and describes its usage and examples. (author)

ARS-Media for excel instruction manual

Science.gov (United States)

ARS-Media for Excel Instruction Manual is the instruction manual that explains how to use the Excel spreadsheet ARS-Media for Excel application. ARS-Media for Excel Instruction Manual is provided as a pdf file....

Development of a SCAT data management manual

International Nuclear Information System (INIS)

Lamarche, A.; Owens, E.H.

2005-01-01

The Shoreline Cleanup Assessment Technique (SCAT) is a commonly used method in North America to document oiling conditions in the aftermath of an oil spill. The data generated by SCAT can support all aspects of the process needed to develop and apply shoreline treatment methods such as planning treatment strategies, selecting treatment methods, providing detailed instructions to response personnel and evaluating the response effort. In order to be effective, SCAT data must be validated, entered within computerized systems, and transformed into support documents such as maps, tables and reports. This paper describes the development of a guidance manual for SCAT data coordinators and spill response managers that use the results of SCAT data. Guidance is presented for emergency procedures that enable the generation of minimal, but adequate, SCAT data management services. The creation of the manual involved the development of formal descriptions of the role, responsibilities and abilities of the SCAT data management team. The manual provides solution to several data processing issues, including those related to the presence of multiple parallel bands of oil within a segment of shoreline. Summary tables were created to report the length of oiled shoreline by oiling category and to present surface oiling characteristics in overview maps. The manual also includes details on how SCAT data is used for response planning, decision making and to support operations. 12 refs., 7 tabs., 8 figs

Programmer's manual for CAMCON: Compliance Assessment Methodology CONtroller

International Nuclear Information System (INIS)

Rechard, R.P.; Gilkey, A.P.; Rudeen, D.K.; Byle, K.A.; Iuzzolino, H.J.

1993-05-01

CAMCON, the Compliance Assessment Methodology CONtroller, is an analysis system that assists in assessing the compliance of the Waste Isolation Pilot Plant (WIPP) with applicable long-term regulations of the US Environmental Protection Agency, including Subpart B of the Environmental Standards for the Management and Disposal of spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191 and 40CFR268.6, which is the portion of the Land Disposal Restrictions implementing the Resource, Conservative, and Recovery Act of 1976, as amended that states the conditions for disposal of hazardous chemical wastes. This manual provides an architectural overview of the CAMCON system. Furthermore this manual presents guidelines and presents suggestions for programmers developing the many different types of software necessary to investigate various events and physical processes of the WIPP. These guidelines include user interface requirements, minimum quality assurance requirements, coding style suggestions, and the use of numerous software libraries developed specifically for or adapted for the CAMCON system

Polarized proton target-III. Operations manual, revision B

International Nuclear Information System (INIS)

Hill, D.; Moretti, A.; Onesto, F.; Rynes, P.

1978-01-01

The manual presented contains certain standard operating procedures for the vacuum, cryogenic, and electronic systems of PPT-III. In total, these systems comprise the following major divisions: (1) the target cryostat; (2) the 4 He pumping system; (3) the 3 He pumping system; (4) the remote monitors and controls; (5) the microwave system; (6) the magnet and power supply; (7) the computerized polarization monitor; (8) the 4 He liquefier and gas recovery system; and (9) miscellaneous auxiliary equipment

Faktor Risiko Manual Handling dengan Keluhan Nyeri Punggung Bawah Pembuat Batu Bata

Directory of Open Access Journals (Sweden)

Heru Subaris Kasjono

2017-08-01

Full Text Available During done manual work handling for objects work hard, it will cause risk of injury or cause musculoskeletal systems. Risk assessment manual work handling with the methods indicators key-Leitmerkmal Method (LMM intended to know the relationship between time, burden, attitudes of the body, and working conditions manual handling with complaints of the lower back pain at all stages making bricks perceived maker bricks. The kind of research used is surveyed such data is cross sectional. The data taken by lower back pain questionnaire assisted examination physically by nurses and checklist Key-LMM. Analysis relations use the spearman. The results of research acquired at variable time manual handling based frequency raised or operation the transfer of on stage excavation raw materials, the formation and drying bricks there are relations with complaints of  low back pain with p value each are 0,039, 0,047, 0,038 while on the variables of working conditions manual handling in stage excavation raw materials obtained p value of 0,028 with so it can be said there was a correlation between working conditions manual handling with complaints low back pain. A variable load manual handling and attitudes of the body manual handling do not relate in significant to lower back pain all stages making bricks. Conclusion researchers that the variable time manual handling relate in significant with complaints lower back pain in stage excavation raw materials, the formation and drying bricks, while the phase processing raw materials that there was no correlation, in a variable load manual handling and attitudes of the body manual handling all these stage there was no correlation with complaints lower back pain, while variable working conditions manual handling only in stage excavation the raw materials there are relations with complaints lower back pain in the third stage other there was no correlation.

EAI 8400 - Manual of the D5LA-2-2 macro-assembler

International Nuclear Information System (INIS)

Roux, Pierre

1968-01-01

The assembly language is a symbolic language specific to the EAI 8400 calculation system. This manual presents the overall rules to write a program with this language. However, the symbolic code of machine instructions and their effect are not given in this manual. The language described here corresponds to the specifications of the version 5B of the assembler. This manual presents first the general rules of the symbolic language writing (the source language) and details the pseudo- and macro-instructions. The assembler's job is briefly described in the introduction

National Ignition Facility TestController for automated and manual testing

Energy Technology Data Exchange (ETDEWEB)

Zielinski, Jason, E-mail: fishler2@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

2012-12-15

The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.

National Ignition Facility TestController for automated and manual testing

International Nuclear Information System (INIS)

Zielinski, Jason

2012-01-01

The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.