ALARA in European nuclear installations

International Nuclear Information System (INIS)

Lefaure, C.; Croft, J.; Pfeffer, W.; Zeevaert, T.

1995-01-01

For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe

ALARA in European nuclear installations

Energy Technology Data Exchange (ETDEWEB)

Lefaure, C. [CEPN, Fontenay-Aux-Roses (France); Croft, J. [NRPB, Chilton, Didcot (United Kingdom); Pfeffer, W. [GRS, Koeln (Germany); Zeevaert, T. [SCK/CEN, Mol (Belgium)

1995-03-01

For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe.

BNL ALARA center's development of a computerized Radiological Assessment and Design System (RADS)

International Nuclear Information System (INIS)

Dionne, B.J.; Connelly, J.M.

1993-01-01

The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation at DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of open-quotes good-practice documentsclose quotes will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called open-quotes Radiological Assessment and Design Systemclose quotes (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analysis, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative ratings of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

ALARA review for the decontamination and decommissioning of the 233-S pipe trench

International Nuclear Information System (INIS)

Kornish, M.J.

1998-01-01

The 233-S Facility was completed in 1955 to expand plutonium production by further concentrating the plutonium nitrate product solution from the Reduction Oxidation (REDOX) Plant. The facility is radiologically contaminated because of operations and accidents. Isolation from REDOX and removal of the product transfer lines from the pipe trench is the second step in the decontamination and decommissioning of the entire 233-S Facility. The work scope is to isolate all piping from REDOX and then to remove all the piping/equipment from the pipe trench. The building is presently a Hazard Category 2 Nuclear Facility. A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure No. 1.22, Planning Radiological Work, when radiological conditions exceed trigger levels. The level of contamination inside the pipe trench and the process fluid piping is unknown. The potential exists to exceed the level of loose surface contamination, which requires a formal ALARA review when opening the pipe trench and cutting of piping commences. This ALARA review is for task instruction 1997-03-18-009 Revision 1, 233-S Pipe Trench Decon and Pipe Removal

Alara applied to iter design and operation

International Nuclear Information System (INIS)

Uzan-Elbez, Joelle; Rodriguez-Rodrigo, Lina; Porfiri, Maria Teresa; Taylor, Neil; Gordon, Charles; Garin, Pascal; Girard, Jean-Philippe

2005-01-01

Based on the existing data on ITER and the safety options for licensing ITER in Cadarache, the present work assesses the application of the as-low-as-reasonably-achievable (ALARA) principle, as it has been implemented in the design of ITER and will be applied during ITER operation, as well as the compliance of the design with EUR/96-29 directive and regulation applicable in France. The preliminary occupational radiation exposure estimate gives a value of about 250 man mSv/a, which is half the annual target for ITER and comes essentially from maintenance activities. Some examples of the approach are presented

As low as is reasonably achievable (ALARA) studies relative to the NWTS program

International Nuclear Information System (INIS)

Abrams, L.A.; Schlegel, R.L.; Sullivan, R.P.

1977-10-01

The history of development of the as-low-as-is-reasonably achievable (ALARA) concept and ALARA criteria for radiation exposures as applied to both off-site (environmental) and on-site (occupational) exposures at nuclear power plants are reviewed. The current status of activities within the various federal agencies directed toward developing ALARA criteria for other areas of the nuclear fuel cycle is presented. Based on the historical development, the present activities, and on discussions with numerous people involved in this area, the future development of ALARA criteria and implications for the National Waste Terminal Storage (NWTS) Program is forecast. Environmental ALARA criteria which relate to minimizing radiation to the surrounding populaltion are discussed along with current occupational ALARA criteria and quidelines for risk-benefit assessments that are under development and recommendations to assure that evolving ALARA concepts are periodically brought up to date and that such concepts be made available to those subcontractors who have responsibility for design and operation of a repository. An annotated bibliography of some 83 sources giving information on ALARA criteria and its application is included

As low as is reasonably achievable (ALARA) studies relative to the NWTS program

Energy Technology Data Exchange (ETDEWEB)

Abrams, L.A.; Schlegel, R.L.; Sullivan, R.P.

1977-10-01

The history of development of the as-low-as-is-reasonably achievable (ALARA) concept and ALARA criteria for radiation exposures as applied to both off-site (environmental) and on-site (occupational) exposures at nuclear power plants are reviewed. The current status of activities within the various federal agencies directed toward developing ALARA criteria for other areas of the nuclear fuel cycle is presented. Based on the historical development, the present activities, and on discussions with numerous people involved in this area, the future development of ALARA criteria and implications for the National Waste Terminal Storage (NWTS) Program is forecast. Environmental ALARA criteria which relate to minimizing radiation to the surrounding populaltion are discussed along with current occupational ALARA criteria and quidelines for risk-benefit assessments that are under development and recommendations to assure that evolving ALARA concepts are periodically brought up to date and that such concepts be made available to those subcontractors who have responsibility for design and operation of a repository. An annotated bibliography of some 83 sources giving information on ALARA criteria and its application is included. (JRD)

Preoperational ALARA walk-down at the Shearon Harris Nuclear Power Plant

International Nuclear Information System (INIS)

Greene, D.W.

1987-01-01

Carolina Power and Light Company's Shearon Harris Nuclear Power Plant will enter commercial operation in 19987. During its design and construction a number of reviews were performed to ensure that personnel exposures in the completed plant would be ALARA. The final review in this process consisted of a comprehensive walk-down of plant radiation controlled areas by health physics, operations, maintenance, and engineering personnel. The walk-down project was conducted over a 12-month period using detailed criteria and checklists. This article describes the project, presents examples of the criteria that were used, and list the problems that were identified for resolution as well as the good ALARA design features that were incorporated into the plant

ALARA review for the 202-S plutonium loadout hood stabilization

International Nuclear Information System (INIS)

Patch, R.F.

2000-01-01

This as low as reasonably achievable (ALARA) review provides a description of the engineering and administrative controls used to manage personnel exposures, control contamination levels, and control airborne radioactivity concentrations while conducting stabilization of the Reduction-Oxidation (REDOX) Facility plutonium loadout hood and associated piping, and the isolation of the ER-8 ventilation system

Proceedings of the Department of Energy ALARA Workshop

International Nuclear Information System (INIS)

Dionne, B.J.; Baum, J.W.

1992-01-01

The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE's field office and contractor personnel about the Office of Health's programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors' facilities, regulatory aspects of ALARA programs, and DOE Headquarters' ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors' ALARA programs. Individual papers are indexed separately

Proceedings of the Department of Energy ALARA Workshop

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Baum, J.W. [comps.

1992-12-31

The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE`s field office and contractor personnel about the Office of Health`s programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors` facilities, regulatory aspects of ALARA programs, and DOE Headquarters` ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors` ALARA programs. Individual papers are indexed separately.

Proceedings of the Department of Energy ALARA Workshop

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Baum, J.W. (comps.)

1992-01-01

The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE's field office and contractor personnel about the Office of Health's programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors' facilities, regulatory aspects of ALARA programs, and DOE Headquarters' ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors' ALARA programs. Individual papers are indexed separately.

ALARA at nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.

1991-01-01

Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

Management organization and administration for ALARA

International Nuclear Information System (INIS)

Kathren, R.L.

1982-01-01

The fundamentals of organizational structure and administration as applied to the goal of keeping occupational radiation exposures as low as reasonably achievable are discussed, including consideration of management commitment, organizational separation of health physics functions, reporting levels, designation of responsibility and authority and adequacy of personnel and funding. Examples of good and poor organizational structures are shown, and the role and implementation of ALARA committees, effective communications, and review and audit processes are discussed. (author)

Optimization (ALARA) of radiation protection at Department of Energy facilities

International Nuclear Information System (INIS)

Weadock, A.A.; Jones, C.R.

1992-01-01

Maintaining worker and public exposures As Low As Reasonably Achievable (ALARA) is a key objective of the Department of Energy (DOE). Responsibility for occupational ALARA program policy and guidance resides within the DOE Office of Health. Current Office of Health initiatives related to ALARA include the development of additional regulatory guidance related to ALARA program implementation at DOE contractor facilities, the review of ALARA program status at various facilities and the production of technical reports summarizing this status, and the support of various mechanisms to improve communication among the DOE ALARA community. The Office of Health also monitors revisions to radiogenic risk estimates and radiation protection recommendations to evaluate adequacy of current DOE limits and impacts of potentially revised limits. (author)

Alara and radiodiagnostics

International Nuclear Information System (INIS)

Vano, E.; Gonzalez, L.; Wall, B.F.

1989-01-01

Specific items of diagnostic radiology facing the application to the ALARA approach are described, there differentiating among workers and patients. The convenience of assessing monetary values for the person. Sv in both cases is emphasized. The paper analyses some of the different steps to be considered in the optimization of diagnostic radiology installations, namely, rooms design and equipment selection, possibly modifications in installations currently working, requesting of radiological examinations, performing examinations and information exploitation. Some practical matters related to workers and patients are discussed, quoting several specific examples of optimization. The paper suggests, as conclusion, some practical guidelines of the stages to be covered along with the application of the ALARA approach

ALARA review for the decontamination and decommissioning of the 233-S P.R. can loadout and decontamination

International Nuclear Information System (INIS)

Kornish, J.M.

1998-01-01

The 233-S Facility was completed in 1955 to expand plutonium production by further concentrating the plutonium nitrate product solution from the Reduction Oxidation (REDOX) Plant. The facility is radiologically contaminated because of operations and accidents. The building is presently a Hazard Category 2 Nuclear Facility. Disassembly of the loadout hood and its associated equipment may be done in parallel with the isolation of 233-S from REDOX via the pipe trench equipment removal. The work scope is to remove the entire loadout hood from the Product Receiver (P.R.) Can Loadout and Decon Room inside the 233-S Facility. A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure 1.22, Planning Radiological Work, when radiological conditions exceed trigger levels. The level of contamination inside the loadout hood and its associated equipment is unknown. The potential exists to exceed the level of loose surface contamination, which requires a formal ALARA review when opening the loadout hood and disassembly commences. This ALARA review is for the task instruction 1997-03-18-010 Revision 0, 233-S Loadout Hood Decon and Dismantlement

ALARA for the practical person

International Nuclear Information System (INIS)

Kathren, R.L.

1991-01-01

The increasing significance of ALARA in recent years has spawned numerous articles and complex technological means to achieve as low as reasonably achievable. The available body of literature on ALARA has grown so large and complex that it is an overwhelming and virtually impossible task for a single individual to remain abreast of it. Regulatory requirements and interpretations of ALARA further add to the difficulties of the operational radiation protection staff seeking ALARA. The practical person can, however, promote and provide ALARA by recalling and applying certain simple principles, including the following, which will be discussed in depth: (1) ALARA is basic and fundamental to any program of radiological protection, and as such the ALARA program or practices must be specifically identifiable. (2) ALARA is a never ending quest, and much like the speed of light or halving the distance to the goal, can really never be reached in a theoretical sense. (3) ALARA is not necessarily synonymous with dose reduction, and certainly does not involve ever continuous reduction in dose. (4) There is no single monetary value applicable to a unit of dose; rather each incremental unit of dose must be examined in the total context of the exposure situation. (5) ALARA involves professional opinion and judgment; responsible and qualified professional health physicists may differ in their opinions as to what constitutes ALARA

EAN - The European ALARA Network; EAN - Le Reseau ALARA Europeen

Energy Technology Data Exchange (ETDEWEB)

Schmitt-Hanning, A. [Office federal de la radioprotection (BfS) (Germany); Crouail, P.; Drouet, F. [Centre d' etude sur l' evaluation de la protection dans le domaine nucleaire (CEPN) (France); Shaw, P. [Agence de protection sanitaire (HPA) (United Kingdom); Vermeersch, F. [EAN, Centre d' etude de l' energie nucleaire (SCK-CEN) (Belgium)

2010-11-15

The optimisation of radiation protection, or ALARA principle, which requires that exposures to ionising radiation be kept as low as reasonably achievable taking into account economic and societal factors, is the cornerstone of the radiation protection system since the late eighties. For many years now, cooperation of experts from different professional backgrounds and different organisations in the European ALARA Network (EAN) has significantly contributed to the development of the ALARA principle and its practical implementation in a range of radiation protection areas in Europe. This contribution presents the evolution and key activities of EAN as well as its mode of operation aiming at sharing experience and disseminating the ALARA culture in all relevant domains. It also describes the new challenges facing EAN and the strategic objectives of the Network for the forthcoming years. (author)

ALARA implementation throughout project life cycle

Energy Technology Data Exchange (ETDEWEB)

Haynes, M.J. [Ontario Hydro, Whitby, Ontario (Canada)

1995-03-01

A strength of radiation protection programs generally has been endorsement and application of the ALARA principle. In Ontario Hydro, which currently operates 20 commercial size nuclear units, great strides have been made in the last three decades in reducing occupational radiation exposure per unit of electricity generated. This paper will discuss specific applications of elements of the overall ALARA program which have most contributed to dose reduction as the nuclear program has expanded. This includes such things as management commitment, ALARA application in the design phase and major rehabilitation work, the benefits of the self protection concept, a specific example of elimination (or reduction) of the source term and the importance of dose targets. Finally, it is concluded that the major opportunities for further improvements may lie in the area of information management.

Expert systems for assisting in design reviews

International Nuclear Information System (INIS)

Brtis, J.S.; Johnson, W.J.; Weber, N.; Naser, J.

1990-01-01

This paper discusses Sargent and Lundy's (S and L's) use of expert system technologies to computerize the procedures used for engineering design reviews. This paper discusses expert systems and the advantages that result from using them to computerize the decision-making process. This paper also discusses the design review expert systems that S and L has developed to perform fire protection and ALARA (as low as reasonably achievable) design reviews, and is currently developing for the Electric Power Research Institute (EPRI) to perform 10 CFR 50.59 safety reviews

ALARA Review of the Activation/Repair of Fire Detectors in Zone Three at the 233-S Facility

International Nuclear Information System (INIS)

Kornish, M.J.

1998-07-01

A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure 1.22, 'Planning Radiological Work', when radiological conditions exceed trigger levels. The level of contamination inside the viewing room meets this criterion. This ALARA review is for task instruction 1997-03-18-005-8.3.3 (mini task instruction to a living work package), 'Instructions for D ampersand D Support of Fire Detector Troubleshooting and Minor Maintenance Work at 233-S,' and DynCorp 2G-98-7207C, '233-S Reconnect Smoke Detectors Zone 3.' The Radiological Work Permit (RWP) request broke these two task instructions into four separate tasks. The four tasks identified in the RWP request were used to estimate airborne concentrations and the total exposure

Application of the ALARA principle to the bleed condenser relief valve replacement project

International Nuclear Information System (INIS)

Wong, T.; Kraft, J.

1997-01-01

Darlington Nuclear Generating Division's achievements in radiation dose performance can be attributed, in part, to adherence to the ALARA principle. The station's ALARA program, which is an integral part of the safety culture, derives its strength from a strong and unwavering commitment by the site Vice President. This commitment is supported by performance standards and an accountability system which holds managers and supervisors responsible for dose performance. A LAN-based hazard and dose information system with site-wide accessibility was established to facilitate work planning and exposure control. The principle of dose optimization is fully integrated into the work management process and includes work planning, progress monitoring and post-job review. An integrated performance assessment and reporting system also provides timely feedback to management on dose performance. An example of the ALARA program was the bleed condenser relieve valve replacement project. Pre-job ALARA review meetings for the project were held with supervisory staff and technicians to discuss job details and dose reduction measures. All work groups were required to prepare a detailed step be step task safety analysis (TSA). The trades and engineering staff were requested to critique the TSA and suggest ways of reducing dose. Over 30 practical ALARA suggestions were received and adopted for implementation. Daily meetings were held to review job progress and the effectiveness exposure control. A post-job ALARA review was held at the conclusion of each project to obtain feedback and lessons learned. All improvement suggestions were reviewed for implementation during subsequent installations. As a result of the ALARA initiatives, significant dose savings were achieved. The normalized dose expenditure has been reduced from 9.6 rem for the first installation to 6.9 rem for the fourth and last installation. (author)

Project W-320 ALARA Plan

International Nuclear Information System (INIS)

Harty, W.M.

1995-01-01

This supporting document establishes the As Low As Reasonable Achievable (ALARA) Plan to be followed during Sluicing Project W-320 design and construction activities to minimize personnel exposure to radiation and hazardous materials

Project W-320 ALARA Plan

Energy Technology Data Exchange (ETDEWEB)

Harty, W.M.

1995-06-06

This supporting document establishes the As Low As Reasonable Achievable (ALARA) Plan to be followed during Sluicing Project W-320 design and construction activities to minimize personnel exposure to radiation and hazardous materials.

The european ALARA network

International Nuclear Information System (INIS)

Croueail, P.; Lefaure, C.; Croft, J.

2000-01-01

Throughout the 1980s and early 1990s the European Commission sponsored projects on the understanding and practical implementation of the ALARA principle. These projects helped ensure that ALARA was integrated into many organisations radiation protection programmes, particularly in the nuclear industry. However there was still much to be done in the non-nuclear sector, as well as for the management of internal exposure. Therefore, the European Commission decided to set up, as of the first January 1996, a European ALARA Network (EAN) whose main goals are to: Further promote ALARA within non nuclear industry, research and the nuclear cycle; Provide a means for feedback experience and the exchange and dissemination of good radiological protection practices in these areas; Initiate proposals for research projects and workshops on topics dealing with optimisation of radiological protection for all types of occupational exposure. The Network has a Steering Committee of experts from 11 countries, with CEPN being the co-ordinator. Twice yearly, the EAN products for the international community a European ALARA Newsletter that reaches several thousand individuals or institutions, mainly in Europe. Each year since 1997, the EAN has organised an ALARA workshop attended by 60 to 80 experts from about ten countries. The first three Workshops were devoted to: ALARA and Decommissioning (1997, Saclay, France), Good Radiation Practices in Industry and Research (1998, Chilton, United Kingdam), and ALARA and Internal Exposure (1999, Munich, Germany). Each of these Workshops gave rise to sets of recommendations to the European Commission which included proposals for further research, modification of regulations, and actions to support feedback experience within the member states. (author)

Strengthening ALARA approach in work management at Krsko NPP

International Nuclear Information System (INIS)

Breznik, B.; Kovac, Z.; Sirola, P.

1999-01-01

As Low As Reasonably Achievable (ALARA) occupational exposures at nuclear power plants should be included in work management as a concept. There are world-wide trends required by the utilities for improved design, operation and maintenance. Within the period of seventeen years of plant operation maintaining low radiation exposures requires additional efforts. The benefit of this effort should be reducing risks to nuclear workers, better work planning and performance. The Krsko Plant ALARA organisations has been revised recently and built on different levels of the hierarchy. The goal is to promote good industry practice and the management of work on primary systems. The established ALARA programme describes the objectives and defines the procedures and tools for its implementation. Brief presentation of the programme as well as organisational responsibilities of dedicated ALARA committee and working groups is the scope of this paper. The management tools and ALARA indicators are discussed to implement the programme and to evaluate the results.(author)

ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

1991-05-01

Promoting the exchange of information related to implementation of the As Low As Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report, prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health, is the second in a series of bibliographies on dose reduction at DOE facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a specific focus towards DOE facilities. Facility types and activities covered in the scope of this report include: radioactive waste; uranium enrichment; fuel fabrication, storage, and reprocessing; facility decommissioning; hot laboratories; tritium production; research, test and production reactors; weapons fabrication and testing; and accelerators. Material on improved shielding design, decontamination, containments, robotics, job planning, improved operational techniques, and other topics has also been included. This volume (Volume 2 of the series) contains 127 abstracts numbered from 69 through 195, as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface. Information that the reader feels should be included in the next volume of this bibliography should be submitted to the BNL ALARA Center

ALARA review of the maintenance and repair jobs of repetitive high radiation dose at Kori Unit 3 and 4

International Nuclear Information System (INIS)

Cho, Y.H.; Moon, J.H.; Kang, C.S.; Lee, J.S.; Lee, D.H.

2003-01-01

The policy of maintaining occupational radiation dose (ORD) as low as reasonably achievable (ALARA) requires the effective reduction of ORD in the phases of design as well as operation of nuclear power plants. It has been identified that a predominant portion of ORD arises during maintenance and repair operations at nuclear power plants. The cost-effective reduction of ORD cannot be achieved without a comprehensive analysis of accumulated ORD data of existing nuclear power plants. To identify the jobs of repetitive high ORD, the ORD data of Kori Units 3 and 4 over 10-year period from 1986 to 1995 were compiled into the PC-based ORD database program. As the radiation job classification structure, 26 main jobs are considered, most of which are further subdivided into detailed jobs. According to the order of the collective dose values for 26 main jobs, 10 jobs of high collective dose are identified. As an ALARA review, then, top 10 jobs of high collective dose are statistically analyzed with regard to 1) dose rate, 2) crew number and 3) job frequency that are the factors determining the collective dose for the radiation job of interest. Through the ALARA review, main reasons causing to high collective dose values are identified as follows. The high collective dose of RCP maintenance job is mainly due to the large crew number and the high job frequency. The characteristics of refueling job are similar to those of RCP maintenance job. However, the high collective doses of SG-related jobs such as S/G nozzle dam job, S/G man-way job and S/G tube maintenance job are mainly due to high radiation dose rate. (author)

ALARA review for the deactivation of 105-N Lift Station

International Nuclear Information System (INIS)

Nellesen, A.L.

1997-01-01

This ALARA review provides a description of the engineering and administrative controls used to manage personnel exposure and to control contamination levels and airborne radioactivity concentrations, while removing water, sludge, stabilizing surfaces, and all other associated work involved in the deactivation of the 105-N Lift Station. The lift station was used as a sump and received contaminated water from the 105-N Fuel Storage Basin weirs and contaminated drains in the 105-N Building. During operation water from the lift station was pumped to the 1310-N and 1325-N cribs. Deactivation of the lift station is a critical step in completing the deactivation of N-Area

Application of the ALARA process in the regulation of nuclear activities

International Nuclear Information System (INIS)

1991-05-01

In this report the historical and conceptual basis of the ALARA process has been reviewed. The application solely of a prescriptive approach, particularly a rigorous quantitative approach to the decision-making process, has been questioned. While the Committees recognize the value of quantitative techniques they strongly emphasize that application of the ALARA concept is a much broader process for the determination of acceptable levels of protection. An ALARA process should take into account social and economic factors that are not quantifiable and involve representation of all those having a legitimate interest in the results of the process

ALARA in radioactive waste management- Summary and recommendations of the 11. European ALARA Network Workshop

International Nuclear Information System (INIS)

Shaw, P.; Crouail, P.; Drouet, F.

2008-01-01

The 11. European ALARA Network (E.A.N.) workshop on 'ALARA in radioactive waste management' took place in Athens (Greece) in April 2008. The aim of that workshop was to focus on the implementation of the ALARA principle with regard to occupational and public exposures arising from the management of radioactive waste in all sectors (nuclear, medical, industrial, etc.). This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. Individual presentations (papers and slides) are available to download from the E.A.N. web site (http://www.eu-alara.net). Based on report backs from the groups and discussions with all the participants, five formal recommendations have been formulated. These recommendations, addressed to international organisations (International Atomic Energy Agency, European Commission, Nuclear Energy Agency), national authorities, national and local stake holders and to E.A.N. itself, deal with the following themes: international guidance on ALARA in radioactive waste management, harmonization issues at the international level, ALARA approach in non-nuclear waste management, 'broader approach' in the radioactive waste management process, stake holder involvement. The objective of this paper is to present the main conclusions and the five recommendations produced during the workshop. (authors)

ALARA application in Spanish NPP's. New approach

International Nuclear Information System (INIS)

O'Donnel, P.; Labarta, T.; Amor, I.

1996-01-01

One main objective of all nuclear installations is to underlie the principle of optimization. The focus in the application of this principle varies considerably, from cost-benefit techniques in the design phases to commitment, attitude and motivation in operation. The ALARA principle should permeate the entire organisation of the company during operation. Management should be the first link of a chain originating with explicit corporate commitment, leading to increasingly specific decisions, finally to reach those who are responsible for actual performance of each task. The safety culture is an element integrating the mentality that is to prevail throughout the organisation. The organisation shall contribute to incorporating the principle of optimization in all plant operations and all phases of activity. Management's commitment and motivation are transferred to all the workers and organisations involved. The ALARA commitment naturally extends to all outside organisations. The ultimate objective is to reduce collective doses through the promotion and enforcing of an ALARA culture and compliance with the operating collective dose objectives. (author)

Pacific Northwest Laboratory ALARA Report for Calendar Year 1993

International Nuclear Information System (INIS)

Keller, S.L.

1994-07-01

This report provides summary results of the Calendar Year (CY) 1993 As Low As Reasonably Achievable (ALARA) Program at the Pacific Northwest Laboratory (PNL). This report includes information regarding whole-body exposures to radiation, and skin contaminations. The collective whole-body radiation dose to employees during 1993 was 0.58 person-sievert (58 person-rem). This dose was 11 percent lower than the projected dose of 0.65 person-sievert (65 person-rem). The Radiation Protection Section's Field Dosimetry Services group projected that no PNL employee's dose would exceed 0.02 sievert (2 rem) based on dosimeters processed during the year; no worker actually exceeded the limit by the end of CY 1993. There were 15 reported cases of skin contamination for PNL employees during 1993. This number of 60 percent of the projected total of 25 cases. There were an additional 21 cases of personal-effects contamination to PNL staff: Nine of these contamination events occurred at the 324 Building, nine occurred at the 325 Building, one occurred in the 327 Building, one occurred in the 3720 Building, and one occurred in the 326 Building. Line management set numerous challenging and production ALARA goals for their facilities. Appendix A describes the final status of the 1993 ALARA goals. Appendix B describes the radiological ALARA goals for 1994. The Radiation Protection Section of the Laboratory Safety Dept. routinely perform audits of radiological ALARA requirements for specific facilities with significant potential for exposure. These ALARA audits are part of a comprehensive safety audit of the facility, designed to evaluate and improve total safety performance

ALARA Center of Technology -- resource guide

International Nuclear Information System (INIS)

Waggoner, L.O.

1998-01-01

The purpose is to provide a source of information that can be used to assist personnel in the planning, training, and execution of radiological work using the principles of ALARA. This document is not intended to replace HNF or WHC Control Manual requirements. The ALARA Tools-List provides detailed information on the use and procurement of engineered controls, mockup training guidelines, and good radiological work practices that have been proven to be ALARA

ALARA Center of Technology -- resource guide

Energy Technology Data Exchange (ETDEWEB)

Waggoner, L.O.

1998-02-05

The purpose is to provide a source of information that can be used to assist personnel in the planning, training, and execution of radiological work using the principles of ALARA. This document is not intended to replace HNF or WHC Control Manual requirements. The ALARA Tools-List provides detailed information on the use and procurement of engineered controls, mockup training guidelines, and good radiological work practices that have been proven to be ALARA.

ALARA/ALARP distinguished

International Nuclear Information System (INIS)

Riley, P.

1992-01-01

In the United Kingdom the term ALARA, ''as low as reasonably achievable'' and the term ALARP ''as low as reasonably practicable'' are used in regulations, in conditions in licenses, in assessment principles and in guidance notes used in the nuclear industry. In fact the ALARA principle is a cornerstone on which much of radiation protection regulation is based. The words ''reasonably practicable'' in ALARP have an established meaning in UK law and are used extensively in statutes and regulations, in particular The Health and Safety Act 1974. The Select Committee of the House of Lords on the European Communities in 1986 concluded that public opinion will play a much larger part in deciding the future of nuclear power than is usual with questions of science and technology. Under the circumstances it is important to industry and the general public for the terms used in legislation to be clear and unambiguous. This paper by distinguishing the terms ALARA/ALARP, sets the scene for a more disciplined use of the terms. (author)

BNL ALARA Center: ALARA Notes, No. 9

International Nuclear Information System (INIS)

Khan, T.A.; Xie, J.W.; Beckman, M.C.

1994-02-01

This issue of the Brookhaven National Laboratory's Alara Notes includes the agenda for the Third International Workshop on ALARA and specific instructions on the use of the on-line fax-on-demand service provided by BNL. Other topics included in this issue are: (1) A discussion of low-level discharges from Canadian nuclear plants, (2) Safety issues at French nuclear plants, (3) Acoustic emission as a means of leak detection, (4) Replacement of steam generators at Doel-3, Beaznau, and North Anna-1, (5) Remote handling equipment at Bruce, (6) EPRI's low level waste program, (7) Radiation protection during concrete repairs at Savannah River, (8) Reactor vessel stud removal/repair at Comanche Peak-1, (9) Rework of reactor coolant pump motors, (10) Restoration of service water at North Anna-1 and -2, (11) Steam generator tubing problems at Mihama-1, (12) Full system decontamination at Indian Point-2, (13) Chemical decontamination at Browns Ferry-2, and (14) Inspection methodolody in France and Japan

Integrating ALARA into work planning and organization

International Nuclear Information System (INIS)

Croft, J.R.; Robb, J.D.

1993-01-01

This paper presents various organizational structures and systematic approaches that can be of benefit in integrating ALARA into work planning and organization. It is possible to have elegant policy statements, procedures and organizations and yet fail to implement ALARA effectively. The real key to success in ALARA work management is to recognize that ALARA is primarily a way of thinking and to secure the commitment of individuals at all levels within the organization, from senior management to workers carrying out specific tasks. The authors explain that the recommendations of ICRP Publication 60 will have an impact and will maintain the downward pressure on individual doses. 6 figs

Effective use of metrics in an ALARA program

International Nuclear Information System (INIS)

Bates, B.B. Jr.

1996-01-01

ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include; external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting and processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific ''indicators''. To choose the site-specific indicators that will be tracked and trended requires careful review. This required the end users to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that customers can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. It is now also a tool to communicate the status of the radiation protection program to facility managers. Finally it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, ''user friendly'', software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics

Proposal of organisation and ALARA procedures for maintenance site: application to replacement of steam generator; Propositions d'organisation et procedures ALARA pour la preparation des chantiers de maintenance: application au RGV

Energy Technology Data Exchange (ETDEWEB)

Lochard, J; Lefaure, C

1989-08-01

This report proposes generic organization and ALARA procedures for preparing a maintenance site at a NPP. After a short description of the ALARA principle, it describes the proposition for French sites. They are grouped according to the following: motivation, organisation, means. They are illustrated by the example of steam generator replacement. Three special points concerning preparation of the site are developed: education; training of operators; review of the project.

Radiation worker: the ALARA key

International Nuclear Information System (INIS)

Weedon, R.R.

1985-01-01

As low as reasonably achievable (ALARA) is a simple concept that has come to be a complicated and expensive regulatory goal. There are essentially three factors that can be manipulated to achieve ALARA: (1) radionuclide inventory (source), (2) physical arrangement (primarily distance and shielding); (3) radiation worker performance (radiation safety responsibilities and functions). Of these three elements, item 3 is utilized the least and yet has the greatest potential for reducing exposure per dollar expended. By establishing a relationship with radiation workers consisting of credible leadership and expecting the radiation workers to be responsible for specific elements of radiological safety. Health Physics can gain a degree of cooperation and performance that will provide significant ALARA gains at a very small expense

ALARA and radiation protection optimization status of Cernavoda NPP

International Nuclear Information System (INIS)

Hau, D.I.

2000-01-01

ALARA in Radiation Protection is specifically applied as a tool in lowering B the risk of high exposure when performing necessary activities by reducing the doses as much and as reasonably possible. Is ALARA also a matter of IMAGE? ALARA is one of the main aspects that contributes to forming the image of a certain facility. Many experiences in the world show a decrease in the collective dose per station after proper ALARA implementation. This trend is more relevant for 'adult' nuclear sites. At Cernavoda NPP the authorization process itself included implementation of an effective ALARA program. (author)

VISIPLAN 3D ALARA planning and communication tool

International Nuclear Information System (INIS)

Vermeersch, F.

2006-01-01

Human operations are required in nuclear installation, during maintenance, outage, repair and decommissioning. This leads to the exposure of the worker to radiation. It is clear that these operations must be performed according to the ALARA principle (to reduce the dose As Low As Reasonably Achievable). The person responsible for planning the job needs to evaluate different scenarios based on the exposure of the worker. This involves the manipulation of a lot of information specific to the work place such as the geometry, materials, radiological and technical boundary conditions to assess the dose. A lot of communication between the ALARA stakeholders is needed during this pre-job study. A communication that can be cumbersome and tedious when based on written documents and paper plans. The use of 3D calculation and simulation tools provide a solution to this problem. They provide an excellent means to make the above mentioned process more efficient and effective by calculating and visualising the environment and the associated radiological risk. The VISIPLAN 3D ALARA planning tool is developed and designed by SCK-CEN as a dose assessment tool enabling the user to calculate the dose in a 3D environment for work scenarios. This software is very successful in the ALARA field. At present 22 companies in Europe use the VISIPLAN software in the field of dose assessment in maintenance and decommissioning. Recent developments and applications are discussed

Applied ALARA techniques

International Nuclear Information System (INIS)

Waggoner, L.O.

1998-01-01

The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work

Applied ALARA techniques

Energy Technology Data Exchange (ETDEWEB)

Waggoner, L.O.

1998-02-05

The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work.

Overview, what is ALARA? Are we there?

International Nuclear Information System (INIS)

Baum, J.W.

1987-01-01

As low as reasonably achievable (ALARA) in radiation protection at nuclear power plants is a complex criterion involving decisions requiring both professional judgement and quantitation. Professional judgement has been emphasized in most plants to date. However, unless quantitative studies are made it will be difficult to judge if doses at US plants are ALARA. An ALARA assessment for each plant is suggested, which would include evaluations of both qualitative, e.g., organizational, and quantitative, e.g., cost-benefit or cost-effectiveness, efforts. 15 refs., 4 tabs

Gentilly - 2 NGS ALARA program

International Nuclear Information System (INIS)

Rheaume, Michel R.

1998-01-01

This is a slide-based oral presentation given to the COG/IAEA: Fifth technical committee meeting on 'Exchange of operating experience of pressurized heavy water reactors' held in Mangalia, Romania on 7-10 September 1998. The operation experience of Gentilly -1 and Gentilly - 2 nuclear power stations is summarized. The radiation protection philosophy is addressed, the orange/yellow/green RP qualifications are explained and the ALARA Program objectives are described. The criteria used to develop the Gentilly - 2 station ALARA Program are presented. The program is based on: strong Hydro Quebec commitments, organization (responsibilities well defined); ALARA Committee; tools; procedures; good documentation. Description of the program is given then in details. Measures for dose and radioactive sources reduction are presented. Collective doses recorded at Gentilly - 2 between 1984 and 1997 are plotted and figures are given in a table

The Alara principle in backfitting Borssele

International Nuclear Information System (INIS)

Leurs, C.J.

1998-01-01

An extensive backfitting program, the Modifications Project, was carried out at the Borssele Nuclear Power Station. It involved sixteen modifications to technical systems. The scope of activities, and the dose rates encountered in places where work was to be performed, made it obvious from the outset that a high collective dose had to be anticipated. As a consequence, radiation protection within the project was organized in such a way that applicable radiation protection principles were applied in all phases of the project. From the point of view of radiation protection, the Modifications Project had to be subdivided into three phases, i.e., a conceptual design phase in which mainly the justification principle was applied; the engineering phase in which the Alara principle was employed; the execution phase in which management of the (internal) dose limits had to be observed in addition to the Alara principle. Throughout all project phases, radiation protection considerations and results were documented in so-called Alara reports and radiation protection checklists. As a result of the strictest possible observance of radiation protection principles in all phases of the project, a collective dose of 2505 mSv was achieved, which stands for a reduction by a factor of 4 compared to the very first estimate. In view of the scope and complex nature of the activities involved, and the radiation levels in the Borssele Nuclear Power Station, this is an excellent result. (orig.) [de

Methodology for making environmental as low as reasonably achievable (ALARA) determinations

International Nuclear Information System (INIS)

Brown, R.C.; Speer, D.R.

1982-01-01

An overall evaluation concept for use in making differential cost-benefit analyses in environmental as low as reasonably achievable (ALARA) determinations is being implemented by Rockwell Hanford Operations. This evaluation includes consideration of seven categories: (1) capital costs; (2) operating costs; (3) state of the art; (4) safety; (5) accident or upset consequences; (6) reliability, operability, and maintainability; and (7) decommissionability. Appropriate weighting factors for each of these categories are under development so that ALARA determinations can be made by comparing scores of alternative proposals for facility design, operations, and upgrade. This method of evaluation circumvents the traditional basis of a stated monetary sum per person-rem of dose commitment. This alternative was generated by advice from legal counsel who advised against formally pursuing this avenue of approach to ALARA for environmental and occupational dose commitments

ALARA and an integrated approach to radiation protection

International Nuclear Information System (INIS)

Hendee, W.R.; Edwards, F.M.

1986-01-01

Exposures of individuals to ionizing radiation have been restricted for many years by a number of guidelines and rules developed by various advisory and regulatory groups. Accompanying these restrictions has been an evolving principle that exposures to individuals and groups should be kept as low as reasonably achievable (ALARA), consistent with provision of the benefits of radiation use to society. Although the ALARA concept is a laudable goal in principle, its implementation in a clinical facility has not been a straightforward process. Problems of implementing ALARA have been confounded further by the efforts of regulatory agencies to incorporate the ALARA concept into regulations governing radiation exposures. To facilitate the implementation of ALARA as a workable construct in a clinical facility, guidelines are needed for its application to both individual and collective exposures to radiation. The provision of such guidelines, including action and inaction levels for both individual and collective exposures, are presented here

ALARA training at INSTN

International Nuclear Information System (INIS)

Nolibe, D.; Lefaure, C.

1994-01-01

Since 1990 the CEPN, the National Radiological Protection Board and the INSTN organized for the first time in Europe one teaching specifically established to radioprotection optimization. This training has allowed to spread the experience of the best european specialists while guaranteeing a wide exchange between the participants coming from different countries. At the national level the training ALARA goes on at the INSTN-Saclay. Its aim is to give base notions, the methods and the tools allowing the implementation of the ALARA concept, and to privilege the exchange between the participants coming from different horizons. 2 refs., 2 figs

ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

1991-03-01

This report is the second in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at US Department of Energy (DOE) facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the US Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health to include DOE nuclear facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy Data Base, and reprints of published articles provided by the authors. Information that the reader feels should be included in the next volume of this bibliography may be submitted to the BNL ALARA Center. These abstracts, which have a bearing on dose reduction, consolidates information from publications pertinent to Radiological Engineers and Operational Health Physicists. Volume 2 contains 127 abstracts numbered from 69 through 195 as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface

Environmental ALARA Program at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.

1993-01-01

The Savannah River Site (SRS) follows the ALARA (As Low As Reasonably Achievable) philosophy of keeping radiation doses to the general public as low as practical by minimizing radioactive releases to the environment. SRS accomplishes this goal by establishing challenging sitewide and area-specific Environmental ALARA Release Guides and trending radioactive releases against these guides on a monthly basis. The SRS Environmental ALARA Program, mandated by DOE Order 5400.5, is a dose-based program that has gone through many changes and improvements in recent years. A description of the SRS Environmental ALARA Program and its performance is presented in this paper. Recent SRS studies of the ''Zero Release'' option also are described

Application of the ALARA concept to the field situation

International Nuclear Information System (INIS)

Johnson, La Mar J.; Ahlquist, A. John

1978-01-01

It has been a long accepted practice in radiation protection that exposure to radiation should not only meet legal requirements but should be as far below these requirements as is reasonably achievable (ALARA). The ALARA concept is difficult to define, thus, there is a tendency by regulatory agencies (often at the request of the regulated) to attach a number to ALARA for environmental considerations. Presently, there are proposals to apply numbers to ALARA for soils contaminated by transuranics. Our actual field experience is determining ALARA for a large-scale land decontamination project suggests ALARA for contaminated soils cannot be determined on the basis of a single number. This paper will focus on the factors that were considered in determining the land had been decontaminated to ALARA. Details of the paper will include difficulties in determining contamination levels in the soil, dollar and man-power costs to remove contaminated soil, time constraints on the analytical procedures, safety considerations, depth of contamination versus costs to remove that contamination, disposal costs and considerations, and likelihood of additional undiscovered contamination. This experience suggests that numbers ought to be developed but should be used as goals or as a basis for decisions and not as blanket rules for all situations. (author)

Proposal of organisation and ALARA procedures for maintenance site: application to replacement of steam generator

International Nuclear Information System (INIS)

Lochard, J.; Lefaure, C.

1989-08-01

This report proposes generic organization and ALARA procedures for preparing a maintenance site at a NPP. After a short description of the ALARA principle, it describes the proposition for French sites. They are grouped according to the following: motivation, organisation, means. They are illustrated by the example of steam generator replacement. Three special points concerning preparation of the site are developed: education; training of operators; review of the project

Westinghouse Hanford Company ALARA year-end report, Calendar Year 1994: Revision 3A, Radiological engineering and ALARA

International Nuclear Information System (INIS)

Berglund, O.D.

1995-06-01

It has long been the US Department of Energy's (DOE's) Policy that radiation doses should be maintained as far below the dose limits as is reasonably achievable. This policy, known as the ''ALARA Principle of radiation protection,'' maintains that radiation exposures should be maintained as low as reasonably achievable, taking into account social, technical, economic, practical, and public policy considerations. The ALARA Principle is based on the hypothesis that even very low radiation doses carry some risk. As a result, it is not enough to maintain doses at/or slightly below limits; the lower the doses, the lower the risks. Because it is not possible to reduce all doses at DOE facilities to zero, economic and social factors must be considered to determine the optimal level of radiation doses. According to the ALARA Principle, if doses are too high, resources should be well spent to reduce them. At some point, the resources being spent to maintain low doses are exactly balanced by the risks avoided. Reducing doses below this point results in a misallocation of resources; the resources could be spent elsewhere and have a greater positive impact on health and safety. The objective of the Westinghouse Hanford Company (WHC) ALARA/Contamination Control Improvement Project (CCIP) Program is to manage and control exposures (both individual and collective) to the work force, the general public, and the environment to levels as low as is reasonable using the aforementioned ALARA Principle

ALARA Council: Sharing our resources and experiences to reduce doses at Commonwealth Edison Facilities

Energy Technology Data Exchange (ETDEWEB)

Rescek, F. [Commonwealth Edison Co., Downers Grove, IL (United States)

1995-03-01

Commonwealth Edison Company is an investor-owned utility company supplying electricity to over three million customers (eight million people) in Chicago and northern Illinois, USA. The company operates 16 generating stations which have the capacity to produce 22,522 megawatts of electricity. Six of these generating stations, containing 12 nuclear units, supply 51% of this capacity. The 12 nuclear units are comprised of four General Electric boiling water (BWR-3) reactors, two General Electric BWR-5 reactors, and six Westinghouse four-loop pressurized water reactors (PWR). In August 1993, Commonwealth Edison created an ALARA Council with the responsibility to provide leadership and guidance that results in an effective ALARA Culture within the Nuclear Operations Division. Unlike its predecessor, the Corporate ALARA Committee, the ALARA Council is designed to bring together senior managers from the six nuclear stations and corporate to create a collaborative effort to reduce occupational doses at Commonwealth Edison`s stations.

Using Weibull Distribution Analysis to Evaluate ALARA Performance

International Nuclear Information System (INIS)

Frome, E.L.; Watkins, J.P.; Hagemeyer, D.A.

2009-01-01

As Low as Reasonably Achievable (ALARA) is the underlying principle for protecting nuclear workers from potential health outcomes related to occupational radiation exposure. Radiation protection performance is currently evaluated by measures such as collective dose and average measurable dose, which do not indicate ALARA performance. The purpose of this work is to show how statistical modeling of individual doses using the Weibull distribution can provide objective supplemental performance indicators for comparing ALARA implementation among sites and for insights into ALARA practices within a site. Maximum likelihood methods were employed to estimate the Weibull shape and scale parameters used for performance indicators. The shape parameter reflects the effectiveness of maximizing the number of workers receiving lower doses and is represented as the slope of the fitted line on a Weibull probability plot. Additional performance indicators derived from the model parameters include the 99th percentile and the exceedance fraction. When grouping sites by collective total effective dose equivalent (TEDE) and ranking by 99th percentile with confidence intervals, differences in performance among sites can be readily identified. Applying this methodology will enable more efficient and complete evaluation of the effectiveness of ALARA implementation.

Steam generator replacement from ALARA aspects

International Nuclear Information System (INIS)

Terry, I.; Breznik, B.

2003-01-01

This paper is going to consider radiological related parameters important for steam generator replacement (SGR) implementation. These parameters are identified as ALARA related parameters, owner-contractor relationship, planning, health physics with logistic services, and time required for the replacement. ALARA related parameters such as source or initial dose rate and plant system configuration define the initial conditions for the planning. There is room to optimise work planning. managerial procedures and also the staff during the implementation phase. The overview of these general considerations is based on the following background: using internationally available data and the experience of one of the vendors, i.e. Siemens-Framatome, and management experience of SG replacement which took place at Krsko NPP in the spring of 2000. Generally plant decisions on maintenance or repair procedures under radiation conditions take into account ALARA considerations. But in the main it is difficult to adjudge the results of an ALARA study, usually in the form of a collective dose estimate, because a comparison standard is missing. That is, very often the planned work is of a one-off nature so comparisons are not possible or the scopes are not the same. In such a case the collective doses for other types of work are looked at and a qualitative evaluation is made. In the case of steam generator replacement this is not the case. Over years of steam generator replacements world-wide a standard has been developed gradually. The first part of the following displays an overview of SGR and sets the Krsko SGR in perspective by applying dose analysis. The second part concentrates on the Krsko SGR itself and its ALARA aspects. (authors)

Shippingport station decommissioning project ALARA Program

Energy Technology Data Exchange (ETDEWEB)

Crimi, F.P. [Lockheed Environmental Systems and Technology Co., Houston, TX (United States)

1995-03-01

Properly planned and implemented ALARA programs help to maintain nuclear worker radiation exposures {open_quotes}As Low As Reasonably Achievable.{close_quotes}. This paper describes the ALARA program developed and implemented for the decontamination and decommissioning (D&D) of the Shippingport Atomic Power Station. The elements required for a successful ALARA program are discussed along with examples of good ALARA practices. The Shippingport Atomic Power Station (SAPS) was the first commercial nuclear power plant to be built in the United States. It was located 35 miles northwest of Pittsburgh, PA on the south bank of the Ohio river. The reactor plant achieved initial criticality in December 1959. During its 25-year life, it produced 7.5 billion kilowatts of electricity. The SAPS was shut down in October 1982 and was the first large-scale U.S. nuclear power plant to be totally decommissioned and the site released for unrestricted use. The Decommission Project was estimated to take 1,007 man-rem of radiation exposure and $.98.3 million to complete. Physical decommissioning commenced in September 1985 and was completed in September 1989. The actual man-rem of exposure was 155. The project was completed 6 months ahead of schedule at a cost of $91.3 million.

The European ALARA network. Development, functioning and main activities

International Nuclear Information System (INIS)

Schmitt-Hannig, A.

2009-01-01

The new ICRP recommendations (ICRP 103), and in particular the detailed treatment of optimisation in the ICRP Publication 101, define optimisation of protection as a source-related process aimed at keeping the likelihood of incurred exposures, the number of people exposed and the magnitude of their individual doses as low as reasonably achievable, also below constraints, taking into account economic and societal factors. Practical implementation and further development of the ALARA principle has been achieved for many years now by the successful cooperation of experts from different European organisations; first as pioneers by establishing the European ALARA Network and then by enthusiastically supporting the activities of the network itself. This contribution presents the evolution, operation and key activities of the European ALARA Network (EAN) in the last years; the successful cooperation of experts from different professional backgrounds, advocating the ALARA principle in a range of radiation protection areas, and contributing to its further development by trading experience and networking. The interaction between the EAN and international organisations, which support the ALARA principle by including relevant activities in their work programmes, is described. (orig.)

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Baum, J.W.; Khan, T.A.

1986-10-01

This report is the third in a series of bibliographies supporting the efforts at Brookhaven National Laboratory on dose reduction at nuclear power plants. Abstracts for this report were selected from papers presented at recent technical meetings, journals and research reports reviewed at the BNL ALARA Center, and searches of the DOE/RECON data base on energy-related publications. The references selected for inclusion in the bibliography relate not only to operational health physics topics but also to plant chemistry, stress corrosion cracking, and other aspects of plant operation which have important impacts on occupational exposure. Also included are references to improved design, planning, materials selection and other topics related to what might be called ALARA engineering. Thus, an attempt has been made to cover a broad spectrum of topics related directly or indirectly to occupational exposure reduction. The report contains 252 abstracts and both author and subject indices

What is Alara

International Nuclear Information System (INIS)

Oudiz, A.; Lochard, J.; Lombard, J.; Croft, J.; Fleishman, A.; Webb, G.

1986-09-01

The system of dose limitation recommended by the International Commission on Radiological Protection formulates three radiation protection principles: 1) the so-called justification principle which states that no practice shall be adopted unless its introduction produces a positive net benefit; 2) the so-called optimisation principle which states that all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account; 3) the limitation of individual dose which insures that the dose equivalent to an individual shall not exceed the limits recommended by the ICRP. Acknowledging the fact that these requirements are interrelated, this report is devoted to a presentation of the second principle, assuming that the two other ones are satisfied. As defined by ICRP, the optimisation principle is strictly equivalent with the commonly known ALARA principle (As Low As Reasonably Achievable). ALARA may be considered altogether as a guiding principle for radiological protection management, as well as a procedure allowing the implementation of this principle

ALARA and planning of interventions

Energy Technology Data Exchange (ETDEWEB)

Rocaboy, A. [Electricite de France, Avoine (France)

1995-03-01

The implementation of ALARA programs implies integration of radiation protection criterion at all stages of outage management. Within the framework of its ALARA policy, Electricide de France (EDF) has given an incentive to all of its nuclear power plants to develop {open_quotes}good practices{close_quotes} in this domain, and to exchange their experience by the way of a national feed back file. Among the developments in the field of outage organization, some plants have focused on the planning stage of activities because of its influence on the radiological conditions of interventions and on the good succession of tasks within the radiological controlled areas. This paper presents the experience of Chinon nuclear power plant. At Chinon, we are pursuing this goal through careful outage planning. We want the ALARA program during outages to be part of the overall maintenance task planning. This planning includes the provision of the availability of every safety-related component, and of the variations of water levels in hthereactor and steam generators to take advantage of the shield created by the water. We have developed a computerized data base with the exact position of all the components in the reactor building in order to avoid unnecessary interactions between different tasks performed in the same room. A common language between Operation and Maintenance had been established over the past years, using {open_quotes}Milestones and Corridors{close_quotes}. A real time dose rate counting system enables the Radiation Protection (RP) Department to do an accurate and efficient follow up during the outage for all the {open_quotes}ALARA{close_quotes} maintenance tasks.

Dose reduction through an ALARA program at Almaraz NPP

International Nuclear Information System (INIS)

Leal, A.; Sustacha, D.; Aneiros, J.M.

1987-01-01

Radiation exposure is in keeping with the rate at which nuclear power production is increased. Therefore, it becomes more and more important that nuclear power producing plants develop an effective dose optimization and minimization [as-low-as-rasonably-achievable (ALARA)] program. Although radiation exposure suffered by the workers is carefully kept below administrative limits, there is a moral obligation to keep these exposures as low as possible. This requirement becomes apparent in the ALARA principle, supported and accepted by all countries with nuclear power plants in operation. Empresarios Agrupados (a Spanish architect engineer company) collaborates with nuclear power producing plants in an effort to maintain the collective ALARA doses through the efforts of a group of engineers specializing in dose minimization and optimization techniques. This group is organized as a radiation protection and maintenance team (ALARA team)

Chernobyl information: The ALARA backlash

International Nuclear Information System (INIS)

Samuelsson, C.

2000-01-01

The risk information to the public failed after the Chernobyl accident, also in countries where radiation protection authorities and experts initially enjoyed public confidence. In contrast to many other large accidents, the responsibility for the information failure stays mainly with the authorities and experts themselves, not with the mass media. Many factors together caused the radiation risk information from SSI (Swedish Radiation Protection Institute), and its sister authorities in many other countries, to be confusing and inadequate, despite the best of intentions. The two major malefactors were the handling of food contamination restrictions and the short-sighted risk optimisation by applying the ALARA principle. In addition, the assurance that the Chernobyl contamination was fairly harmless made no sense to the layman, as a massive array of controlling procedures was enforced simultaneously. The food regulations became unfortunately focused on becquerel per kilogram limits instead of the primary goal, a dose reduction per year, corresponding to an yearly intake of Cs-137. The lesson learned is that the risk significant long-term intake ambition must be understood and digested by laymen and media, before any secondary limits, e.g. the activity concentration of foodstuffs expressed as becquerel per kg, for controlling or trading purposes, are introduced. As it were, the experts and authorities lost credibility, due to what people considered as ambiguities. The concept of ALARA (As Low As Readily Achievable) is in the backbone of every ionising radiation expert, and a useful strategy for optimising dose burdens during controlled situations. In connection to the Chernobyl accident many advices to the public was given based on the ALARA principle. 'Rinse leafy vegetables' sounds at first very reasonable, cheap and innocent, but if the averted dose is low, such an advice should not be given. The individual dose-reduction should be weighted against all negative

The organization of ALARA program at a DOE facility

International Nuclear Information System (INIS)

Setaro, J.A.

1992-01-01

The organization of an ALARA Program at a DOE Facility (Oak Ridge National Laboratory), it's relationship with laboratory management, facility operators, and the radiation protection program is described. The use of chartered ALARA committees at two distinct levels is discussed

ALARA issues arising for safety and security of radiation sources and security screening devices - Summary and recommendations of the 12. European ALARA network workshop

International Nuclear Information System (INIS)

Shaw, P.; Crouail, P.; Drouet, F.

2010-01-01

The 12. European ALARA Network (EAN) workshop on 'ALARA issues arising for safety and security of radiation sources and security screening devices' took place in Vienna (Austria) in October 2009. The aim of that workshop was to consider how the implementation of ALARA3, in terms of planned and emergency situations, involving worker and public doses, is affected by the introduction of security-related measures. In the case of new equipment and procedures, there was also the question of whether exposures arising from security screening devices can be justified and optimised. This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. During their discussions, the working groups identified recommendations dealing with the following topics: the implementation of the Code of Conduct and HASS4 - ensuring ALARA; balancing security and safety - how to achieve an optimum solution; the management of an emergency exposure situation from an ALARA perspective; the justification and optimisation of the use of security devices. The objective of this paper is to present the main conclusions and recommendations produced during the workshop. Individual presentations (papers and slides) as well as the reports from the working groups are available to download on the EAN web site (http://www.eu-alara.net). (authors)

Fluor Hanford ALARA Center is a D and D Resource

International Nuclear Information System (INIS)

Waggoner, L.O.

2008-01-01

The mission at the Hanford Nuclear Reservation changed when the last reactor plant was shut down in 1989 and work was started to place all the facilities in a safe condition and begin decontamination, deactivation, decommissioning, and demolition (D and D). These facilities consisted of old shutdown reactor plants, spent fuel pools, processing facilities, and 177 underground tanks containing 53 million gallons of highly radioactive and toxic liquids and sludge. New skills were needed by the workforce to accomplish this mission. By 1995, workers were in the process of getting the facilities in a safe condition and it became obvious improvements were needed in their tools, equipment and work practices. The Hanford ALARA Program looked good on paper, but did little to help contractors that were working in the field. The Radiological Control Director decided that the ALARA program needed to be upgraded and a significant improvement could be made if workers had a place they could visit that had samples of the latest technology and could talk to experienced personnel who have had success doing D and D work. Two senior health physics personnel who had many years experience in doing radiological work were chosen to obtain tools and equipment from vendors and find a location centrally located on the Hanford site. Vendors were asked to loan their latest tools and equipment for display. Most vendors responded and the Hanford ALARA Center of Technology opened on October 1, 1996. Today, the ALARA Center includes a classroom for conducting training and a mockup area with gloveboxes. Two large rooms have a containment tent, several glove bags, samples of fixatives/expandable foam, coating displays, protective clothing, heat stress technology, cutting tools, HEPA filtered vacuums, ventilation units, pumps, hydraulic wrenches, communications equipment, shears, nibblers, shrouded tooling, and several examples of innovative tools developed by the Hanford facilities. See Figures I and

How reasonable is ALARA?

International Nuclear Information System (INIS)

Kiefer, H.

1991-01-01

The linear extrapolation of the established dose-effect relation at higher doses was accepted as a simple working hypothesis to determine dose limits for professional radiation personnel. It has been misused, however, for calculations of population risks in the very low dose region. This lead to an overestimation of radiation hazards by the public, followed by an overregulation of radiation protection. The ALARA recommendations of ICRP - justification of radiation application, optimisation of protection, and protection of the individual, - was aimed at counterpoising this trend and elucidate the aims of radiation protection. But even the ALARA principle will only be successful if it is applied with reason. The lend more weight to reason in radiation protection, an award for FS members is proposed, as well as an anti-award for the most nonsensical action in radiation protection. (orig.) [de

Health physics aspects of advanced reactor licensing reviews

International Nuclear Information System (INIS)

Hinson, C.S.

1995-01-01

The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on open-quotes next-generationclose quotes reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs currently being reviewed by the NRC

Maintaining occupational dose ALARA through work management

International Nuclear Information System (INIS)

Khan, A. H.

1999-01-01

Canadian philosophy in keeping occupational dose ALARA has been to train staff in radiation safety so that they can be fully responsible for participating in minimizing the risks associated with the hazardous work. Senior managers actively promote high standards of performance in dose reduction techniques as a means for integrating ALARA into the operation and maintenance of the station by all personnel. Minimizing radiation dose is accomplished by applying cost effective work management techniques such as Job Safety Analysis, pre-job briefings and establishing and achieving radiation dose goals. Radiation dose goals are used as a management tool for involving all work groups in reducing doses as well as providing a means of assessing the effectiveness of dose reduction actions. ALARA, along with conventional safety, is used as a lever to raise the standard of quality of work and to overall build a safety culture. (author). 4 figs

Dose reduction and optimization studies (ALARA) at nuclear power facilities

International Nuclear Information System (INIS)

Baum, J.W.; Meinhold, C.B.

1983-01-01

Brookhaven National Laboratory (BNL) has been commissioned by the Nuclear Regulatory Commission (NRC) to study dose-reduction techniques and effectiveness of as low as reasonably achievable (ALARA) planning at LWR plants. These studies have the following objectives: identify high-dose maintenance tasks; identify dose-reduction techniques; examine incentives for dose reduction; evaluate cost-effectiveness and optimization of dose-reduction techniques; and compile an ALARA handbook on data, engineering modifications, cost-effectiveness calculations, and other information of interest to ALARA practioners

Guide to reducing radiation exposure to as low as reasonably achievable (ALARA)

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.

1980-04-01

This document is designed to provide DOE contractor personnel with general guidance regarding programs and techniques to reduce radiation exposures to as low as reasonably achievable (ALARA). Thus it is directed towards a broad audience, and should have special relevance and interest for operating management as well as radiation protection personnel. It is well recognized that each contractor has needs specific and critical to its radiation protection program. Hence no single set of specific and detailed criteria can be set down as a prescription for achieving the ALARA goal. Rather, general guidance in the form of broad principles is given in order to acquaint management with ALARA needs and concepts. The purpose is to encourage maximum management support of the technical personnel responsible for carrying out day-to-day radiation protection activities. Although primarily written for management, this document also contains technical guidance of potential value to those directly involved in radiation protection activities. Again it should be stressed that what is provided is guidance, and is therefore not mandatory.

Guide to reducing radiation exposure to as low as reasonably achievable (ALARA)

International Nuclear Information System (INIS)

Kathren, R.L.

1980-04-01

This document is designed to provide DOE contractor personnel with general guidance regarding programs and techniques to reduce radiation exposures to as low as reasonably achievable (ALARA). Thus it is directed towards a broad audience, and should have special relevance and interest for operating management as well as radiation protection personnel. It is well recognized that each contractor has needs specific and critical to its radiation protection program. Hence no single set of specific and detailed criteria can be set down as a prescription for achieving the ALARA goal. Rather, general guidance in the form of broad principles is given in order to acquaint management with ALARA needs and concepts. The purpose is to encourage maximum management support of the technical personnel responsible for carrying out day-to-day radiation protection activities. Although primarily written for management, this document also contains technical guidance of potential value to those directly involved in radiation protection activities. Again it should be stressed that what is provided is guidance, and is therefore not mandatory

Health physics manual of good practices for reducing radiation exposure to levels that are as low as reasonably achievable (ALARA)

International Nuclear Information System (INIS)

Herrington, W.N.; Higby, D.P.; Kathren, R.L.; Merwin, S.E.; Stoetzel, G.A.

1988-06-01

A primary objective of the US Department of Energy (DOE) health physics and radiation protection program has been to limit radiation exposures to those levels that are as low as reasonably achievable (ALARA). As a result, the ALARA concept developed into a program and a set of operational principles to ensure that the objective was consistently met. Implementation of these principles required that a guide be produced. The original ALARA guide was issued by DOE in 1980 to promote improved understanding of ALARA concepts within the DOE community and to assist those responsible for operational ALARA activities in attaining their goals. Since 1980, additional guidance has been published by national and international organizations to provide further definition and clarification to ALARA concepts. As basic ALARA experience increased, the value and role of the original guide prompted the DOE Office of Nuclear Safety (ONS) to support a current revision. The revised manual of good practices includes six sections: 1.0 Introduction, 2.0 Administration, 3.0 Optimization, 4.0 Setting and Evaluating ALARA Goals, 5.0 Radiological Design, and 6.0 Conduct of Operations. The manual is directed primarily to contractor and DOE staff who are responsible for conduct and overview of radiation protection and ALARA programs at DOE facilities. The intent is to provide sufficient guidance such that the manual, if followed, will ensure that radiation exposures are maintained as low as reasonably achievable and will establish the basis for a formally structured and auditable program. 118 refs., 16 figs., 3 tabs

Comments on two American justice decisions founded on ALARA

International Nuclear Information System (INIS)

Boehler, M.C.

1996-01-01

The role of the ALARA principle in the American justice is considered as a very important part of the law in evolution. The first decision called 'James decision' was the case of a worker who received a dose under the dose limit and was agreed in his demand. The second one,'Three Miles Island decision', was to refuse the ALARA principle as a norm because it would consider that the justice is more able to pilot a nuclear power plant than competent authorities. These two examples show that the ALARA principle must stay an operational guide and not a legal norm of precautions susceptible to impose sanctions by justice. (N.C.)

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-04-01

The purpose of the Old Hydrofracture Facility (OHF) Tanks Contents Removal Project is to remove the liquid low-level waste from the five underground storage tanks located at OHF and transfer the resulting slurry to the Melton Valley Storage Tanks facility for treatment and disposal. Among the technical objectives for the OHF Project, there is a specific provision to maintain personnel exposures as low as reasonably achievable (ALARA) during each activity of the project and to protect human health and the environment. The estimated doses and anticipated conditions for accomplishing this project are such that an ALARA Plan is necessary to facilitate formal radiological review of the campaign. This ALARA Plan describes the operational steps necessary for accomplishing the job together with the associated radiological impacts and planned controls. Individual and collective dose estimates are also provided for the various tasks. Any significant changes to this plan (i.e., planned exposures that are greater than 10% of original dose estimates) will require formal revision and concurrence from all parties listed on the approval page. Deviations from this plan (i.e., work outside the scope covered by this plan) also require the preparation of a task-specific ALARA Review that will be amended to this plan with concurrence from all parties listed on the approval page

Experiences in ALARA application: 7th parade of maintenance; Experiencias en la aplicacion del criterio ALARA: septima parada de mantenimiento

Energy Technology Data Exchange (ETDEWEB)

Armenta R, M S [Comision Federal de Electricidad, Central Laguna Verde, Veracruz (Mexico)

1991-07-01

The achieved experience with these activities, and all the carried out during the seventh stop but that they are not included here, carried to take a serie of decisions in the ALARA group, of which can be mentioned the following: 1. Definition of goals of collective dose and singular for works, to complete the ALARA commitment toward the occupational exposure personnel of the CLV. 2. To analyze the obtained information, as quick as possible, for using it in similar situations of work (to normalize the obtained results, when this is possible. 3. To coordinate the activities in those that participate different work groups with the end of not hindering the development of the same ones. 4. To establish ALARA responsibles of the works to fulfill functions of: pursuit of the work and information to the workers for their safety.

Report on the PWR-radiation protection/ALARA Committee

Energy Technology Data Exchange (ETDEWEB)

Malone, D.J. [Consumers Power Co., Covert, MI (United States)

1995-03-01

In 1992, representatives from several utilities with operational Pressurized Water Reactors (PWR) formed the PWR-Radiation Protection/ALARA Committee. The mission of the Committee is to facilitate open communications between member utilities relative to radiation protection and ALARA issues such that cost effective dose reduction and radiation protection measures may be instituted. While industry deregulation appears inevitable and inter-utility competition is on the rise, Committee members are fully committed to sharing both positive and negative experiences for the benefit of the health and safety of the radiation worker. Committee meetings provide current operational experiences through members providing Plant status reports, and information relative to programmatic improvements through member presentations and topic specific workshops. The most recent Committee workshop was facilitated to provide members with defined experiences that provide cost effective ALARA performance.

An effective ALARA [As Low As Reasonably Achievable] Awareness Program

International Nuclear Information System (INIS)

Aldridge, T.L.; Hammond, D.A.

1990-10-01

Following the January 1, 1989 issue of the US Department of Energy (DOE) revised Order 5480.1, Chapter XI (DOE 1985), the Westinghouse Hanford Company (Westinghouse Hanford) As Low As Reasonably Achievable (ALARA) Program Office (APO) began an aggressive ALARA Awareness Campaign. The revised DOE Order 5480.11 (DOE 1988) required the documentation and tracking of ALARA practices and principles. This major challenge for compliance to the new requirements necessitated an enhanced awareness of the goals and objectives of the APO. The Westinghouse Hanford APO began the expansion of the ALARA Program. The ''classic concept'' of radiological exposure minimization, which began in the early 1940's, increased in scope to include the new concept of exposure minimization for all hazardous materials and conditions commensurate with sound economics and operating practices. This expansion could only be implemented by bringing about a cultural change. Therefore, the attempt to introduce this change in thinking created a second major challenge for the Westinghouse Hanford APO. The direct result of the identification of these two major goals was the creation of an effective ALARA Awareness for Westinghouse Hanford. This paper describes this program. 3 refs

Integration of Formal Job Hazard Analysis and ALARA Work Practice

CERN Document Server

Nelsen, D P

2002-01-01

ALARA work practices have traditionally centered on reducing radiological exposure and controlling contamination. As such, ALARA policies and procedures are not well suited to a wide range of chemical and human health issues. Assessing relative risk, identifying appropriate engineering/administrative controls and selecting proper Personal Protective Equipment (PPE) for non nuclear work activities extends beyond the limitations of traditional ALARA programs. Forging a comprehensive safety management program in today's (2002) work environment requires a disciplined dialog between health and safety professionals (e.g. safety, engineering, environmental, quality assurance, industrial hygiene, ALARA, etc.) and personnel working in the field. Integrating organizational priorities, maintaining effective pre-planning of work and supporting a team-based approach to safety management represents today's hallmark of safety excellence. Relying on the mandates of any single safety program does not provide industrial hygien...

Health physics aspects of advanced reactor licensing reviews

Energy Technology Data Exchange (ETDEWEB)

Hinson, C.S. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-03-01

The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on {open_quotes}next-generation{close_quotes} reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs currently being reviewed by the NRC.

Dose control and ALARA at nuclear power plants

International Nuclear Information System (INIS)

Xia Yihua; Li Xutong

1999-01-01

With the development of NPPs in China, paying attention to dose control and ALARA at NPPs is very important. The author briefly introduces two primary tasks for exposure control at NPPs, primary consideration of ALARA and the common technical methods. It points out that adoption of some quantitative indicators is useful, but it is important to bear it in mind that these ' values of dose avoided' are situation specific

Application of the Alara principle to the occupationally exposed workers in nuclear power plants

International Nuclear Information System (INIS)

Mueller, W.; Haider, G.

1988-01-01

This report sets down how the Alara (as low as reasonably achievable) principle is applied in radiation protection of the occupationally exposed personnel at light-water reactors in EC countries. In some instances the practices, experiences and results from EC countries are supplemented by the practice in other States (e.g. USA, Sweden). Commencing with a short summary of the legal situation in the Member States of the European Community with regard to Alara, the report describes the framework in which the optimization practice has been developed. The main chapters elaborate in detail how the Alara principle has been put into practice in design and operation in LWRs. The importance of qualification and training of power-plant personnel in relation to optimization of radiation protection is considered and some comparisons are drawn with the US practice. Recommendations are made where reason for modification or harmonization of practices is seen in the conclusions of the different chapters and the overall conclusions and summary of the report

ANI/MAELU engineering inspection criteria 8.3 ALARA

Energy Technology Data Exchange (ETDEWEB)

Schneider, L. [American Nuclear Insurers, West Hardford, CT (United States)

1995-03-01

The purpose of this criteria section is to provide guidelines for programs whose intent is to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA). The success that has been achieved by applying ALARA concepts at nuclear power plants is clearly illustrated by the major reductions in the annual cumulative dose to workers at many sites over the last few years. This success is the combined result of the general maturity of the nuclear industry, the intensive study of dose reduction practices by industry groups, and the successful sharing of experience and practices among plants. Source term reduction should be used as a primary ALARA mechanism. Methods which should be considered include: satellite and cobalt reduction, chemistry control, decontamination, submicron filters, zinc addition, hot spot reduction and permanent or temporary shielding.

ALARA in practice: How is it working

International Nuclear Information System (INIS)

Webb, G.A.M.; Lochard, J.

1984-01-01

At the first CEC scientific seminar on optimisation in 1979 (21) most of the papers were concerned with possible methodologies for quantification of the ALARA concept and difficulties in applying them. Very few gave even theoretical examples of how it could be applied in practice. In contrast, at this second seminar most of the papers are examples of how quantified techniques have been used to assist towards ALARA decisions. This rapporteurs paper examines the quantification frameworks available and how they are being used in practice on the basis of the papers presented at this meeting

Use of metrics in an effective ALARA program

International Nuclear Information System (INIS)

Bates, B.B. Jr.

1996-01-01

ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting an processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific open-quotes indicators.close quotes To choose the site-specific indicators that will be tracked and trended requires careful review. Justification is needed to defend the indicators selected and maybe even stronger justification is needed for those indicators that are available, but not chosen as a metric. Historically, the many different sources of information resided in a plethora of locations. Even the same type of metric had data located in different areas and could not be easily totaled for the entire Site. This required the end user to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that a customer can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. IL is now also a tool to communicate the status of the radiation protection program to facility managers. Finally, it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, open-quotes user friendly,close quotes software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics. These include quarterly performance indicator reports, monthly radiological incident reports, monthly external dose history and goals tracking reports, and the future use of performance indexing

Culture of safety. Indicators of culture of safety. Stage of culture of safety. Optimization of radiating protection. Principle of precaution. Principle ALARA. Procedure ALARA

International Nuclear Information System (INIS)

Mursa, E.

2006-01-01

Object of research: is the theory and practice of optimization of radiating protection according to recommendations of the international organizations, realization of principle ALARA and maintenance of culture of safety (SC) on the nuclear power plant. The purpose of work - to consider the general aspects of realization of principle ALARA, conceptual bases of culture of safety, as principle of management, and practice of their introduction on the nuclear power plant. The work has the experts' report character in which the following questions are presented: The recommendations materials of the IAEA and other international organizations have been assembled, systematized and analyzed. The definitions, characteristics and universal SC features, and also indicators as a problem of parameters and quantitative SC measurements are described in details advanced. The ALARA principles - principle of precaution; not acceptance of zero risk; choice of a principle ALARA; model of acceptable radiation risk are described. The methodology of an estimation of culture of safety level and practical realization of the ALARA principle in separate organization is shown on a practical example. The SC general estimation at a national level in Republic of Moldova have been done. Taking into consideration that now Safety Culture politics are introduced only in relation to APS, in this paper the attempt of application of Safety Culture methodology to Radiological Objects have been made (Oncological Institute of the Republic of Moldova and Special Objects No.5101 and 5102 for a long time Storage of the Radioactive Waste). (authors)

Experiences in ALARA application: 7th parade of maintenance

International Nuclear Information System (INIS)

Armenta R, M.S.

1991-01-01

The achieved experience with these activities, and all the carried out during the seventh stop but that they are not included here, carried to take a serie of decisions in the ALARA group, of which can be mentioned the following: 1. Definition of goals of collective dose and singular for works, to complete the ALARA commitment toward the occupational exposure personnel of the CLV. 2. To analyze the obtained information, as quick as possible, for using it in similar situations of work (to normalize the obtained results, when this is possible. 3. To coordinate the activities in those that participate different work groups with the end of not hindering the development of the same ones. 4. To establish ALARA responsibles of the works to fulfill functions of: pursuit of the work and information to the workers for their safety

Practical quantitative measures of ALARA

International Nuclear Information System (INIS)

Kathren, R.L.; Larson, H.V.

1982-06-01

Twenty specific quantitative measures to assist in evaluating the effectiveness of as low as reasonably achievable (ALARA) programs are described along with their applicability, practicality, advantages, disadvantages, and potential for misinterpretation or dortion. Although no single index or combination of indices is suitable for all facilities, generally, these five: (1) mean individual dose equivalent (MIDE) to the total body from penetrating radiations; (2) statistical distribution of MIDE to the whole body from penetrating radiations; (3) cumulative penetrating whole body dose equivalent; (4) MIDE evaluated by job classification; and (5) MIDE evaluated by work location-apply to most programs. Evaluation of other programs may require other specific dose equivalent based indices, including extremity exposure data, cumulative dose equivalent to organs or to the general population, and nonpenetrating radiation dose equivalents. Certain nondose equivalent indices, such as the size of the radiation or contamination area, may also be used; an airborne activity index based on air concentration, room volume, and radiotoxicity is developed for application in some ALARA programs

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Dionne, B.J.; Lane, S.G.; Baum, J.W.

1991-11-01

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report, prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health, contains the third in a series of bibliographies on dose reduction at DOE facilities. This report also contains abstracts from the two previous volumes. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy Data Base, and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, storage, and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, and accelerators. Material on improved shielding design, decontamination, containments, robotics, job planning, improved operational techniques, and other topics are also included

Improvement of ALARA in Taiwan Nuclear Power Plants

International Nuclear Information System (INIS)

Kao, H. M.; Chang, M.

2006-01-01

Full text: Full text: The ALARA(as low as reasonable achievable ) principle is a basic spirit of radiation safety culture and the most important element of a successful radiation safety program. In recent years, the ALARA principle and practices have been widely applied to the three operating nuclear power plants in Taiwan. Through the effective communication and fully cooperation between the authority and utility, the performance goals of improving radiation safety program have been set, and the implementation plans have been proposed and followed. Taking Chinshan nuclear power station as an example, in 2004, the occupational individual dose was 1.13mSv/ person in average,no one exceeded 20mSv ,and the collective dose was 1.03man-Sv/unit which achieved the best record of BWR plant in Taiwan. The radiation reduction approaches and tools adopted by the plants include removing radiation sources, setting radiation shieding, optimizing and controlling the schedule of radiation practices, considering the occupancy factors, and better administrative management to keep exposure ALARA will be discussed in this paper

Review of ALARA plan for activities at the 105 K-East fuel storage basin

International Nuclear Information System (INIS)

Vargo, G.J.; Durham, J.S.; Hickey, E.E.; Stansbury, P.S.; Cicotte, G.R.

1994-09-01

As part of its ongoing efforts to reduce doses to workers to levels as low as reasonably achievable (ALARA), Westinghouse Hanford Company (WHC) tasked the Health Protection Department of the Pacific Northwest Laboratory (PNL) to review operations at the 105 K-East Fuel Storage Basin (105 K-East). This review included both routine operations and a proposed campaign to encapsulate N-Reactor fuel stored there. This report summarizes the results of PNL's reviews of policy, procedures, and practices for operations at 105 K-East as well as an evaluation of the major sources of occupational radiation exposures. Where possible, data previously collected by WHC and its predecessors were used. In addition, PNL staff developed a three-dimensional model of the radiological environment within 105 K-East to assess the relative contributions of different radiation sources to worker dose and to provide a decision tool for use in evaluating alternative methods of dose rate reduction. The model developed by PNL indicates that for most areas in the basin the primary source of occupational radiation exposure is the contaminated concrete surfaces of the basin near the waterline. Basin cooling water piping represents a significant source in a number of areas, particularly the Technical Viewing Pit. This report contains specific recommendations to reduce the impact of these sources of occupational radiation exposure in 105 K-East. Other recommendations to reduce doses to workers during activities such as filter changes and filter sampling are also included

ALARA trademark 1146 strippable coating

International Nuclear Information System (INIS)

Fricke, V.

1999-01-01

Strippable or temporary coatings are innovative technologies for decontamination that effectively reduce loose contamination at low cost. These coatings have become a viable option during the deactivation and decommissioning of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. The ALARA trademark 1146 strippable coating was demonstrated as part of the Savannah River Site LSDDP and successfully removed transferable (surface) contamination from multiple surfaces (metal and concrete) with an average decontamination factor for alpha contamination of 6.68 and an average percentage of alpha contamination removed of 85.0%. Beta contamination removed was an average DF of 5.55 and an average percentage removed of 82.0%. This paper is an Innovative Technology Summary Report designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They also are designed for readers who may recommend that a technology be considered by prospective users. This Innovative Technology offers a 35% cost savings over the Baseline Technology

ALARA: Progress and prospects

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.

1988-01-01

This paper has two main topics. The first part describes the establishment and work of the ALARA Center; the second part presents some results of studies at the Center with international data on doses at PWR plants. This data then is used to reach a preliminary understanding of some of the factors that are causing high doses at PWRs. This approach should help in reducing occupational exposures in a more effective manner

Man-rem audit - a tool for exposure ALARA at Madras Atomic Power Station

International Nuclear Information System (INIS)

Shivaramakrishnan, N.R.; Eswaran, G.; Gangamohan, M.; Sathish, A.V.; Ramasubramanian, K.V.; Gandhimathinathan, S.; Selvam, S.; Moolya, L.L.

2012-01-01

ALARA - acronym for As Low As Reasonably Achievable, which means making every reasonable effort to maintain exposures to radiation as far below the dose limits as is practical. ICRP has recommended ALARA to be implemented as a formal practice into the System of Dose Limitation, which contains three parts, 1) Justification of practice 2) Optimization 3) Dose Limits. As with the human endeavor, there is always room for improvement. Keeping this in mind, ALARA program is being practiced in our Nuclear Power Plants over the years. There has been a gradual reduction of collective dose in our Nuclear Power Plants due to successful implementation of the ALARA programs. This was possible due to the rigorous application of O and M experience, feedback and active participation of workforce towards ALARA. Furthermore, ALARA is an ongoing continual improvement programme towards collective dose reduction and has enough scope for improvement at any point of time. In order to substantiate the gains of ALARA programme and to improve it further, first time Mam-rem Audit was conducted at MAPS during the month of Sep-Oct 2010. This paper gives the brief outline about the method man-rem audit, its findings, corrective action implementation and the benefits derived from it. Man-rem audit similar to financial audit, serves as a tool for finding out grey areas where improvements is required so that station collective dose can be further optimized. It is one of the identified missions to achieve excellence in area of reducing station collective dose, unplanned exposures and RPP deviation. The scope of this audit is to bring further improvements in the reduction in station collective dose, create more awareness among the employees about ALARA principles and seek valuable suggestions for improvements. Audit team consisting of senior HP persons had one to one interaction with the individuals of the respective section in the field and tried to gather the information from the individual and

LANL Environmental ALARA Program Status Report for CY 2016

Energy Technology Data Exchange (ETDEWEB)

Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mcnaughton, Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-24

Los Alamos National Laboratory (LANL) ensures that radiation exposures to members of the public and the environment from LANL operations, past and present, are below regulatory thresholds and are as low as reasonably achievable (ALARA) through compliance with DOE Order 458.1 Radiation Protection for the Public and the Environment, and LANL Policy 412 Environmental Radiation Protection (LANL2016a). In 2007, a finding (RL.2-F-1) and observation (RL.2-0-1) in the NNSA/ LASO report, September 2007, Release of Property (Land) Containing Residual Radioactive Material Self-Assessment Report, indicated that LANL had no policy or documented process in place for the release of property containing residual radioactive material. In response, LANL developed PD410, Los Alamos National Laboratory Environmental ALARA Program. The most recent version of this document became effective in 2014 (LANL 2014a). The document provides program authorities, responsibilities, descriptions, processes, and thresholds for conducting qualitative and quantitative ALARA analyses for prospective and actual radiation exposures to the public and t o the environment resulting from DOE activities conducted on the LANL site.

Integration of Formal Job Hazard Analysis and ALARA Work Practice

International Nuclear Information System (INIS)

NELSEN, D.P.

2002-01-01

ALARA work practices have traditionally centered on reducing radiological exposure and controlling contamination. As such, ALARA policies and procedures are not well suited to a wide range of chemical and human health issues. Assessing relative risk, identifying appropriate engineering/administrative controls and selecting proper Personal Protective Equipment (PPE) for non nuclear work activities extends beyond the limitations of traditional ALARA programs. Forging a comprehensive safety management program in today's (2002) work environment requires a disciplined dialog between health and safety professionals (e.g. safety, engineering, environmental, quality assurance, industrial hygiene, ALARA, etc.) and personnel working in the field. Integrating organizational priorities, maintaining effective pre-planning of work and supporting a team-based approach to safety management represents today's hallmark of safety excellence. Relying on the mandates of any single safety program does not provide industrial hygiene with the tools necessary to implement an integrated safety program. The establishment of tools and processes capable of sustaining a comprehensive safety program represents a key responsibility of industrial hygiene. Fluor Hanford has built integrated safety management around three programmatic attributes: (1) Integration of radiological, chemical and ergonomic issues under a single program. (2) Continuous improvement in routine communications among work planning/scheduling, job execution and management. (3) Rapid response to changing work conditions, formalized work planning and integrated worker involvement

Computer and computer graphics support for the ALARA program

International Nuclear Information System (INIS)

Paine, D.; Hall, C.J.

1984-01-01

Computer programs have been developed which support three aspects of the ALARA program at Rockwell Hanford Operations (RHO): 1) Setting annual dose and skin contamination goals, 2) Analyzing trends in operational organizations' dose, numbers of skin contaminations, or radiation occurrences, and 3) Presenting graphic displays to enhance worker safety awareness. Programs have been written which search dosemetry files and produce histograms of annual occupational exposure and skin contamination histories utilizing the DISSPLA software or a desk top color graphics terminal. These programs and associated graphics are used to assemble dose and skin contamination information in a summary format so that ALARA teams can assess the past year's performance and establish reduction goals for the coming year. In addition, the graphics provide a management tool for recognizing desirable or undesirable trends in an organization's occupational dose or number of skin contaminations. Desk top graphics capabilities have been used to display safety-related data to enhance management review and worker awareness of radiological and industrial safety conditions in the work area. The following graphs are prepared on a monthly basis: 1) Numbers of skin contaminations company wide and for specific operating organizations within the company, 2) Numbers of radiation occurrences, 3) Dose histories for specific operational organizations, 4) Numbers of OSHA recordable incidents, 5) OSHA recordable incident rates and severity levels and 6) Lost workday cases

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Sullivan, S.G.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1994-01-01

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE`s Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts.

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5

International Nuclear Information System (INIS)

Dionne, B.J.; Sullivan, S.G.; Baum, J.W.

1994-01-01

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts

Department of Energy ALARA implementation guide. Response to the Health Physics Society

Energy Technology Data Exchange (ETDEWEB)

Connelly, J.M. [Dept. of Energy, Washington, DC (United States)

1995-03-01

In the August 1993 Health Physics Society (HPS) newsletter, the HPS Scientific and Public Issues Committee published a Position Statement entitled {open_quotes}Radiation Protection of the Public and the Environment.{close_quotes}. In this article, this HPS committee made the statement that they were deeply concerned by the trend for agencies to incorporate the ALARA concept as a regulatory requirements, without providing specific guidance as to what it means and how to implement it consistently. The HPS position paper was in response to the DOE notice on proposed rulemaking for Title 10 Code of Federal Regulations Part 834, {open_quotes}Radiation Protection of the Public and the Environment{close_quotes} (10 CFR 834). In the notice of proposed rulemaking for 10 CFR 834, the Department of Energy (DOE) defined ALARA as follows: {open_quotes}As used in this part, ALARA is not a dose limit, but rather a process which has the objective of attaining doses as far below the applicable limit of this part as is reasonably achievable{close_quotes} (10 CFR 834.2, p. 16283 of the Federal Register). The HPS position paper continues, {open_quotes}The section goes on to elaborate on what is meant by a process without providing sufficient guidance to assure uniform applicability of the process.{close_quotes}. Although this concern is directed towards the ALARA process as it relates to the environment, the Office of Health, which is responsible for occupational workers, shares the same definition for ALARA.

The application of the ALARA principle: a first assessment

International Nuclear Information System (INIS)

Lochard, J.; Webb, G.A.M.

1984-01-01

What can we learn from practical ALARA studies. On the methodological point of view the different works developed these last years rely upon the two basic ICRP assumptions, i.e.: the linearity of the dose-risk relationship and the optimal resource allocation principle. Furthermore, most authors seem now to assume the multidimensionality of radiological protection problems. This leads to envisage for decision-aiding techniques the enlargement of the cost-benefit method. As for the quantification process of ALARA principle, assessment techniques for both protection costs and levels of exposures of the various groups at risk are well established. Some differences can be however pointed out between authors concerning the monetary valuation of the detriment cost as well as the way to cope with time, probabilistic events and ''other factors'' not directly linked to protection costs and radiological detriment. Further consideration must be given to the exact role ALARA studies have to play in the decision-making process concerning conception and operation of installations. Particular efforts have to be put on the development of adequate data bases and also decision-aiding techniques able to take into account the multidimensionnality of factors involved in practical protection [fr

ALARA at Tyco Health care-Mallinckrodt

International Nuclear Information System (INIS)

Rijpkema, J.

2002-01-01

How to approach the ALARA requirement? That was one of the question in the beginning of the 1990's at the Mallinckrodt site for the preparation of radiopharmaceuticals. This question was raised after the ICRP published their guidelines in the ICRP 60 publication, with the average effective dose limit that was changed from 50 to 20 mSv per year. In the early 1990's the individual effective dose at Mallinckrodt was up to 20 mSv7year and some of the people over this number. As a first result of the discussion Mallinckrodt adopted the 20 mSv/year as being the legal limit, although it finally took over a decade to incorporate this ICRP limit into legislation. A second action was to introduce a site internal limit: if a person would exceed 75% of the legal limit, the person would be restrained from radiation work. This restriction forced everybody to look for solutions to decrease dose and area dose rate. This was the beginning and resulted in nobody exceeding 15 mSv/year after a couple of years and a lower average dose than before, with no extra employees. The second stage in the process of ALARA was a systematic approach of the decrease in personal dose. This systematic approach consists of three phases. The first phase is dose assessment followed by routine measurements. The third phase is the ALARA step. First phase, dose assessment. Normally this could be done in a meeting or even behind the desk: assess the dose per department or per group or per activity. Make a decision on which party will get high priority, medium priority and low priority. Normally this means that the department with the highest dose will get the highest priority. (Author)

Implementation of ALARA radiation protection on the ISS through polyethylene shielding augmentation of the Service Module Crew Quarters

Science.gov (United States)

Shavers, M. R.; Zapp, N.; Barber, R. E.; Wilson, J. W.; Qualls, G.; Toupes, L.; Ramsey, S.; Vinci, V.; Smith, G.; Cucinotta, F. A.

2004-01-01

With 5-7 month long duration missions at 51.6° inclination in Low Earth Orbit, the ionizing radiation levels to which International Space Station (ISS) crewmembers are exposed will be the highest planned occupational exposures in the world. Even with the expectation that regulatory dose limits will not be exceeded during a single tour of duty aboard the ISS, the "as low as reasonably achievable" (ALARA) precept requires that radiological risks be minimized when possible through a dose optimization process. Judicious placement of efficient shielding materials in locations where crewmembers sleep, rest, or work is an important means for implementing ALARA for spaceflight. Polyethylene (C nH n) is a relatively inexpensive, stable, and, with a low atomic number, an effective shielding material that has been certified for use aboard the ISS. Several designs for placement of slabs or walls of polyethylene have been evaluated for radiation exposure reduction in the Crew Quarters (CQ) of the Zvezda (Star) Service Module. Optimization of shield designs relies on accurate characterization of the expected primary and secondary particle environment and modeling of the predicted radiobiological responses of critical organs and tissues. Results of the studies shown herein indicate that 20% or more reduction in equivalent dose to the CQ occupant is achievable. These results suggest that shielding design and risk analysis are necessary measures for reducing long-term radiological risks to ISS inhabitants and for meeting legal ALARA requirements. Verification of shield concepts requires results from specific designs to be compared with onboard dosimetry.

ALARA radiation protection applications at NPP A1 decommissioning using VISPLAN planning tool

International Nuclear Information System (INIS)

Slavik, O.; Kucharova, D.; Listjak, M.

2005-01-01

The SCK.CEN developed during the BR3 reactor decommissioning a graphical interfaced 3D dose assessment tool aimed at the above mentioned dose optimization problems. The tool was improved further and commercialized under the name VISIPLAN 3D ALARA planning tool. The use of VISIPLAN tool at NPP A1 decommissioning was advised by EDF within the IAEA TCP SLR/4008 project missions as a component of a 3D technological chain ensuring acquisition and evaluation of digitized information leading to ALARA optimisation of the developed decommissioning working procedures (see Fig. 1). VISIPLAN license was purchased by IAEA and granted to VUJE and NPP A1 within the IAEA TCP project SLR/4008, covering also the necessary basic and advanced training (at NPP A1 real decommissioning environment), and is currently used by VUJE analysts at NPP A1 decommissioning as an ALARA tool for intervention planning and optimisation. The VISIPLAN allows a fast dose assessment for work planned in a radioactive environment. The calculations are based on a 3D model of the work place. This PC-based tool is user friendly and calculates a detailed dose account for different work scenarios defined by the ALARA analyst, taking into account worker position, work duration and subsequent geometry and source distribution changes. The VISIPLAN methodology is described. The VISIPLAN tool was applied to several ALARA studies carried out by the VUJE within development and analysis of various Work Programs for NPP Al decommissioning tasks. The applications ranged from simpler to complex ALARA planning tasks covering simple shielding applications to selection of the most suitable order of complex working procedures. Removal of inner liners from underground reservoirs 6/1 and 6/2 as well as Dismantling of pipes and components from a (hostile) 60 m corridor are described. (authors)

ALARA cost/benefit analysis at Union Electric company using the ARP/AI methodology

International Nuclear Information System (INIS)

Williams, M.C.

1987-01-01

This paper describes the development of a specific method for justification of expenditures associated with reducing occupational radiation exposure to as low as reasonably achievable (ALARA). This methodology is based on the concepts of the Apparebt Reduction Potential (ARP) and Achievability index (AI) as described in NUREG/CR-0446, Union Eletric's corporate planning model and the EPRI Model for dose rate buildup with reactor operating life. The ARP provides a screening test to determine if there is a need for ALARA expenditures based on actual or predicted exposure rates and/or dose experience. The AI is a means of assessing all costs and all benefits, even though they are expressed in different units of measurement such as person-rem and dollars, to determine if ALARA expenditures are justified and their value. This method of cost/benefit analysis can be applied by any company or organization utilizing site-specific exposure and dose rate data, and incorporating consideration of administrative exposure controls which may vary from organization to organization. Specific example cases are presented and compared to other methodologies for ALARA cost/benefit analysis

ALARA tools and performance indicators at Cernavoda NPP

International Nuclear Information System (INIS)

Chitu, C.; Popescu, V.; Simionov, V.

2009-01-01

Work efficiency is an area of high concern to nuclear power plant operators. Job planning has to be done so that there will be enough time for ALARA actions to be implemented. The control of the activities involving radiological risk is part of ALARA Process. An effective control supposes the implementation of a process to systematically identify the activities performed in radiological areas. Plant Performance Indicators related to ionizing radiation exposure have been established to improve station safe performance. They are assessed and reported periodically to reflect the safe operation objectives. If target values are exceeded 'abnormal condition reports' are generated. Corrective and preventive actions aim at work planning, technical aspects, and human performance. All the staff is informed about these events and corrective actions described through the training program are implemented. (authors)

Clinical application of 'Justification' and 'Optimization' principle of ALARA in pediatric CT imaging: "How many children can be protected from unnecessary radiation?".

Science.gov (United States)

Sodhi, Kushaljit S; Krishna, Satheesh; Saxena, Akshay K; Sinha, Anindita; Khandelwal, Niranjan; Lee, Edward Y

2015-09-01

Practice of ALARA (as low as reasonably achievable) principle in the developed world is currently well established. However, there is striking lack of published data regarding such experience in the developing countries. Therefore, the goal of this study is to prospectively evaluate CT request forms to assess how many children could be protected from harmful radiation exposure if 'Justification' and 'Optimization' principles of ALARA are applied before obtaining CT imaging in a developing country. This can save children from potential radiation risks including development of brain cancer and leukemia. Consecutive CT request forms over a six month study period (May 16, 2013 to November 15, 2013) in a tertiary pediatric children's hospital in India were prospectively reviewed by two pediatric radiologists before obtaining CT imaging. First, 'Justification' of CT was evaluated and then 'Optimization' was applied for evaluation of appropriateness of the requested CT studies. The number (and percentage) of CT studies avoided by applying 'Justification' and 'Optimization' principle of ALARA were calculated. The difference in number of declined and optimized CT requests between CT requests from inpatient and outpatient departments was compared using Chi-Square test. A total of 1302 consecutive CT request forms were received during the study period. Some of the request forms (n=86; 6.61%) had requests for more than one (multiple) anatomical regions, hence, a total of 1392 different anatomical CT requests were received. Based on evaluation of the CT request forms for 'Justification' and 'Optimization' principle of ALARA by pediatric radiology reviewers, 111 individual anatomic part CT requests from 105 pediatric patients were avoided. Therefore, 8.06% (105 out of 1302 pediatric patients) were protected from unnecessary or additional radiation exposure.The rates of declined or optimized CT requests from inpatient department was significantly higher than that from outpatient

Cobalt reduction of NSSS valve hardfacings for ALARA

Energy Technology Data Exchange (ETDEWEB)

Kim, Joo Hak; Lee, Sang Sub [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-07-01

This report informs NSSS designer that replacement of materials is one of the major means of ALARA implementation, and describes that NSSS valves with high-cobalt hardfacing are significant contributors to post-shutdown radiation fields caused by activation of cobalt-59 to cobalt-60. Generic procedures for implementing cobalt reduction programs for valves are presented. Discussions are presented of the general and specific design requirements for valve hardfacing in nuclear service. The nuclear safety issues involved with changing valve hardfacing materials are discussed. The common methods used to deposit hardfacing materials are described together with an explanation of the wear measurements. Wear resistance, corrosion resistance, friction coefficient, and mechanical properties of candidate hardfacing alloys are given. World-wide nuclear utility experience with cobalt-free hardfacing alloys is described. The use of low-cobalt or cobalt-free alloys in other nuclear plant components is described. 17 figs., 38 tabs., 18 refs. (Author).

Cobalt reduction of NSSS valve hardfacings for ALARA

International Nuclear Information System (INIS)

Kim, Joo Hak; Lee, Sang Sub

1994-07-01

This report informs NSSS designer that replacement of materials is one of the major means of ALARA implementation, and describes that NSSS valves with high-cobalt hardfacing are significant contributors to post-shutdown radiation fields caused by activation of cobalt-59 to cobalt-60. Generic procedures for implementing cobalt reduction programs for valves are presented. Discussions are presented of the general and specific design requirements for valve hardfacing in nuclear service. The nuclear safety issues involved with changing valve hardfacing materials are discussed. The common methods used to deposit hardfacing materials are described together with an explanation of the wear measurements. Wear resistance, corrosion resistance, friction coefficient, and mechanical properties of candidate hardfacing alloys are given. World-wide nuclear utility experience with cobalt-free hardfacing alloys is described. The use of low-cobalt or cobalt-free alloys in other nuclear plant components is described. 17 figs., 38 tabs., 18 refs. (Author)

Occupational dose reduction at Department of Energy contractor facilities: Study of ALARA programs

International Nuclear Information System (INIS)

Dionne, B.J.; Meinhold, C.B.; Khan, T.A.; Baum, J.W.

1992-03-01

This report provides the US Department of Energy (DOE) and its contractors with information that will be useful for reducing occupational radiation doses at DOE's nuclear facilities. In 1989 and 1990, health physicists from the Brookhaven National Laboratory's (BNL) ALARA Center visited twelve DOE contractor facilities with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). The health physicists interviewed radiological safety staff, engineers, and training personnel who were responsible for dose control. The status of ALARA practices at the major contractor facilities was compared with the requirements and recommendation in DOE Order 5480.11 ''Radiation Protection for Occupational Workers'' and PNL-6577 ''Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are as Low as Reasonably Achievable.'' The information and data collected are described and examples of successful practices are presented. The findings on the status of the DOE Contractor ALARA Programs are summarized and evaluated. In addition, the supplement to this report contains examples of good-practice documents associated with implementing the major elements of a formally documented ALARA program for a major DOE contractor facility

ALARA approach on Qinshan unit I lower internals recovery project

International Nuclear Information System (INIS)

Wu Meijing; Xu Hongming; Jiang Jianqi; Chen Zhongyu

2000-01-01

Qinshan unit-1 is a 300 Mwe prototype PWR. It has been successfully operating for 4 fuel cycles about 10 years. Some loose parts by the failure of the guide tube of the reactor core neutron flux measurement thimble were observed on the lower structure of Core Barrel during periodical inspection after unloading all fuel assemblies. Qinshan Nuclear Power Company selected Westinghouse Electric Company as contractor to perform the reactor core barrel recovery service after negotiated with 4 world big company. QNPC and Westinghouse worked together to approach the ALARA by increasing water shielding, adding additional steel shielding, fuel pool cleaning and using the long hand tools, remote camera system. The training, mock-up exercise, good personal behavior was greatly contributed to the ALARA approaching. The collective dose and personal exposure of this job were successful controlled by implementing the preset ALARA program. The job was done by the cost of 70 man.mSv collective dose and 3.5 mSv maximum personal exposure despite of the high dose-rate which hot spot in some place is up to several hundred Sv per hour. (author)

The Evaluation of personnel radiation dose and society radiation on RSG-GAS around as proposal determination of ALARA value

International Nuclear Information System (INIS)

Pande Made Udiyani; Puradwi IW

2007-01-01

Each nuclear installation to achieve radiation safety has to meet the ALARA concepts. The ALARA value of a nuclear installation should be enacted by regulator body. ALARA value can be determined by evaluation radiation exposure and dose acceptance of nuclear installation operation. As case study in Indonesia, ALARA assessment in nuclear installation is done at RSG-GAS reactor. Intention of this research is to determine gyration reference assess ALARA by evaluate radiation dose acceptance by RSG-GAS radiation personnel and the influence of RSG-GAS operation to presentation of radiation accepted by society which living around its. ALARA of RSG-GAS determined based on evaluation of measurement data of the radiation doses which is accepted by personnel radiation. While evaluation of radiation doses which is accepted by society in the radius 5 km of the RSG-GAS conducted to data result of calculation using program package of CAP-88 and measurement result with method of carborne survey. Result of radiation dose evaluation obtained which not pass dose definition for the radiation worker that is 50 mSv/year, and for society around RSG-GAS that is 5 mSv/year. Based on the result of evaluation hence obtained value of ALARA for RSG-GAS in value of gyration 17 - 50 mSv/year. (author)

Pacific Northwest Laboratory plan to maintain radiation exposure as low as reasonably achievable (ALARA)

International Nuclear Information System (INIS)

Higby, D.P.; Denovan, J.T.

1982-12-01

This document describes the radiation safety program at the Pacific Northwest Laboratory (PNL). The practices and administrative policies of this program support the principles of ALARA (to maintain radiation exposure as low as reasonably achievable). This document also describes a program to establish safety goals at PNL to help ensure that operations are conducted according to ALARA principles

Ten years of ALARA experience in commercial nuclear pharmacy

International Nuclear Information System (INIS)

Coffey, J.L.; Seifert, K.L.; Green, R.L.; McAnany, P.J.

2002-01-01

The objective of this study was to review ten years of extremity exposure in a growing nuclear pharmacy company and determine those practices that have been most effective in keeping exposures ALARA. The focus of this study was specifically on extremity exposure since whole body exposures have not been as significant. Methods: More than 400 dispensing employees are monitored weekly for extremity exposure. Currently, these employees handle and dispense more than 9,000 Curies (333,000 GBq) of activity ready for use in nuclear medicine procedures each week. The quarterly and annual extremity exposure histories were examined and compared with the introduction of different initiatives to limit these exposures. Changes in the total activity per unit dose were considered as well as the introduction of different compounding practices during this time. An attempt was made to also determine specifically which activities contribute most to the extremity exposure of a dispenser. Procedural changes were reviewed as well as engineering controls such as new shielding materials and designs. Results: A significant conversion of cardiac doses occurred during the time period evaluated. Tc-99m heart agents became the preferred radiopharmaceutical replacing a significant portion of Tl-201 that had been used previously. Tl-201 is still used often in conjunction with a Tc-99m agent. The significance of the switch is the high percentage of dispensed doses for cardiac studies and the higher activities of the Tc-99m agents. A combination of procedural changes and engineering controls (primarily tungsten shielding devices) have been effective in preventing the extremity exposure increase one might expect based on higher activities dispensed per unit dose and the higher energy of Tc-99m compared to Tl-201. One procedural change, the mandatory use of tongs for handling unshielded syringes of radiopharmaceuticals, resulted in a 17% reduction in the average exposure to the extremities

Review of the Safety Design Approaches in Sodium Fast Reactors

International Nuclear Information System (INIS)

Suk, Soo Dong; Lee, Yong Bum

2009-12-01

The principle of the Defense in depth is essential in securing the safety of nuclear power plants, that is, to prevent cores-damaging severs accidents and to minimize the radiological consequences of the accidents 'as low as possible' (ALARA). One of the major design features of sodium fast reactors (SFRs) is that it has a large amount of sodium in the reactor vessel, providing a large heat capacity, such that it is feasible to contain the consequences of sever core damaging accidents in the vessel and primary system boundary. Containment of a severe accident in the primary system boundary, that is called in-vessel retention(IVR), is not a licensing requirement but set up as a design goal in most of the SFR design in the context of risk minimization. The objective of this report is to broadly review and compare the approaches and efforts made in the some of the major SFR designs of the US, Europe and Japan to prevent severe accidents and mitigate their consequences should they occur. Specifically, the subjects described in this report include design criteria or requirements, accident categorization and acceptance criteria, design features to prevent and contain severs accidents

The uniform application of ALARA to all radiation workers

International Nuclear Information System (INIS)

Pomroy, C.

1988-05-01

New information on the dosimetry and epidemiology of atomic bomb survivors suggests that risk estimates may have to be revised upwards. This has focussed increased attention on the ALARA principle. The ICRP believes that ALARA principle is the driving force in keeping average radiation doses low. In practice, the optimization process required for ALARA varies between different sectors of the nuclear industry. For instance, the power utilities have developed procedures for comparing different dose reduction options. Similarly, uranium mine operators have applied optimization techniques to questions concerning ventilation and shielding of ore trucks. Missing from this list however, is the use of a formal optimizing technique in medical and research uses of radioactivity or radiation. Nonetheless, average annual doses to these workers are quite low. An alternative approach to optimization calculation has been suggested, entailing the identification of sub-groups of workers with substantially higher doses to discover the reasons for the higher doses, and to develop means to reduce them to the overall average. Thus maintenance mechanics in nuclear reactors, by the very nature of their jobs, have more potential for higher dose. The utilities are developing procedures to reduce the maintenance mechanics' doses. If the same analysis is applied to medical workers, it is seen that isotope technicians and therapeutic radiology technicians have average doses well above the overall average. The feasibility of some form of optimization process for these categories of workers is discussed

Clinical application of ‘Justification’ and ‘Optimization’ principle of ALARA in pediatric CT imaging: “How many children can be protected from unnecessary radiation?”

International Nuclear Information System (INIS)

Sodhi, Kushaljit S.; Krishna, Satheesh; Saxena, Akshay K.; Sinha, Anindita; Khandelwal, Niranjan; Lee, Edward Y.

2015-01-01

Highlights: • Practice of ALARA (As Low As Reasonably Achievable) principle in the developed world is currently well established. However, there is striking lack of published data regarding such experience in the developing countries. Therefore, the goal of this study is to prospectively evaluate CT request forms to assess how many children could be saved from harmful radiation exposure if ‘Justification’ and ‘Optimization’ principles of ALARA are applied before obtaining CT imaging in a developing country. • A consecutive 1302 CT request forms over a six month study period (May 16, 2013 to November 15, 2013) in a tertiary pediatric children’s hospital in India were prospectively reviewed by two pediatric radiologists before obtaining CT imaging. First, ‘Justification’ of CT was evaluated and then ‘Optimization’ was applied for evaluation of appropriateness of the requested CT studies. The number (and percentage) of CT studies that was avoided by applying ‘Justification’ and ‘Optimization’ principle of ALARA were calculated. The difference in number of declined and optimized CT requests between CT requests from inpatient and outpatient departments was compared using Chi-Square test. • Based on evaluation of the CT request forms for ‘Justification’ and ‘Optimization’ principle of ALARA by pediatric radiology reviewers, 111 individual anatomic part CT requests from 105 pediatric patients were avoided. Therefore, 8.06% (105 out of 1302 pediatric patients) were saved from unnecessary or additional radiation exposure The rates of declined or optimized CT requests from inpatient department was significantly higher than that from outpatient departments (p < 0.05). • To conclude, a substantial number of pediatric patients, particularly coming from inpatients departments, can be saved from unnecessary or additional radiation exposure from CT imaging when ‘Justification’ and ‘Optimization’ principle of ALARA are applied

Design aspects of radiological safety in nuclear facilities

International Nuclear Information System (INIS)

Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

2014-01-01

In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

Cost basis for implementing ALARA programs

International Nuclear Information System (INIS)

Kent, C.E.

1985-01-01

A method of implementing effective ALARA programs is discussed. A basic element of the cost benefit methodology is the valuation of a man-rem. In the program, this is derived from an assessment of radiation exposure risk and societal valuation of harmful effects. The man-rem value is used as an element in the cost benefit analysis. The analysis includes an assessment of the differential man-rem resulting from the action, implementation cost, and operational savings

ALARA in the radiation protection training

International Nuclear Information System (INIS)

Nolibe, D.; Lefaure, Ch.

1998-01-01

This part treats especially the question of the training in radiation protection. The electro nuclear sector has given an ALARA principle culture and succeeded to sensitize each level of hierarchy, but for small industry, the research and the medical world the same method appears more difficult to use. It seems better to reinforce the importance of the competent person and to include a training in radiation protection on the initial formation in numerous professional categories. (N.C.)

Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

International Nuclear Information System (INIS)

Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

1983-12-01

The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals

Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

Energy Technology Data Exchange (ETDEWEB)

Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

1983-12-01

The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals.

Spent Nuclear Fuel Project dose management plan

International Nuclear Information System (INIS)

Bergsman, K.H.

1996-03-01

This dose management plan facilitates meeting the dose management and ALARA requirements applicable to the design activities of the Spent Nuclear Fuel Project, and establishes consistency of information used by multiple subprojects in ALARA evaluations. The method for meeting the ALARA requirements applicable to facility designs involves two components. The first is each Spent Nuclear Fuel Project subproject incorporating ALARA principles, ALARA design optimizations, and ALARA design reviews throughout the design of facilities and equipment. The second component is the Spent Nuclear Fuel Project management providing overall dose management guidance to the subprojects and oversight of the subproject dose management efforts

ALARA and radiation protection optimization status of Cernavoda NPP

International Nuclear Information System (INIS)

Hau, D.I.

2001-01-01

ALARA (As Low As Reasonably Achievable) in Radiation Protection is specifically applied as a tool in lowering the risk of exposure when performing necessary activities, leading to a reduction of individual and collective doses of workers as much and as reasonable possible. (authors)

ALARA [as low as reasonably achievable] engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Daniel, S.W.; Kaplan, E.; Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

1989-09-01

This report is the first in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at DOE facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, and searches of the DOE Energy Data Base. The abstracts included in this report relate to operational health physics as well as other subjects which have a bearing on dose reduction. Facilities covered include: radioactive waste, uranium enrichment, fabrication, unirradiated fissile materials storage, irradiated fissile material storage, reprocessing, decommissioning, recovery, hot laboratories, tritium production, reactors (research, test and production but not power reactors), and accelerators. We have also included material in improved design, materials selection, planning, and other topics which are related to dose-reduction efforts. The report contains 68 abstracts as well as subject and author indices

Development of ADRA

International Nuclear Information System (INIS)

Brtis, J.S.

1987-01-01

All nuclear power plant modifications must be designed in a way that keeps the radiation dose to radiation workers and the public As Low As is Reasonably Achievable (ALARA). This is not only a good design practice, it is required by the NRC in accord with Title 10 of the Code of Federal Regulations). As a result, millions of dollars are spent each year developing, analyzing, and justifying the ALARA design of plant modifications. Providing the necessary design reviews is a major challenge to the industry. In response, Sargent and Lundy has developed ADRA (the ALARA Design Review Assistant), a microcomputer-based system that aids in developing, reviewing, and documenting good ALARA designs. ADRA is now in an early operational stage, undergoing testing at Sargent and Lundy. This paper reviews the findings and results of the ADRA development effort

Alara and work management

International Nuclear Information System (INIS)

Wahlstrom, B.

1989-01-01

All occupational radiation doses come out as a product of dose rates and exposure time, ie man-hours. In most cases there is not very much to be done about the dose rates, but by means of work management a lot can still be achieved. Non-technical factors which have an influence on the radiation doses are, for instance, work planning and co-ordination, training and know-how, optimization of the work force, health physics practice and time scheduling. These work management factors can be put to use at any nuclear power plant, regardless modern and clean or old and hot. As ALARA through work management in most cases means minimization of man-hours, it is worth while in two senses: One can save radiation doses and one can save money at the same time

Towards the development of an ALARA culture

International Nuclear Information System (INIS)

Schieber, C.; Thezee, C.

2000-01-01

The ALARA principle, which states, for each exposure situation, that doses must be kept As Low As Reasonably Achievable, taking into account economic and social factors' represents the basis of the > developed to manage the radiological risk in a responsible manner. The practical implementation of the ALARA principle is complex. It requires defining transaction mechanisms which enable a responsible management of the radiological risk, taking into account, among other things, possible risk transfers in groups and the allocation of protection resources. The players who can take part in radiological risk management are numerous and have different functions: from the authorities to exposed workers, together with company managers. They all possess specific knowledge and have objectives which are not necessarily compatible. The transactions and negotiations initiated between these players during decision-taking relative to exposure management will therefore only be efficient and productive if there exists both a mutual comprehension of individual objectives and a readiness to collaborate on a common objective: keeping the residual risk at a level both acceptable to, and accepted by, the various parties involved. A fundamental element of this process therefore lies in the development among the various players concerned of a common culture with respect to radiological risks and the methods used for their management, in order to facilitate transactions by the sharing of a common language and system of values. A possible definition of > could be: >. Based on this statement, the paper presents, illustrated by the experience of the French Utility Electricite de France, the main components which should enter into consideration for the development of an ALARA culture for the management of occupational exposures. It concludes on the necessity to construct and transmit a common patrimony of a radiological risk management system comprising the scientific and technical knowledge

Control of occupational radiation exposures in TVA nuclear power plants - design and operating philosophy

International Nuclear Information System (INIS)

Belvin, E.A.; Lyon, M.; Beasley, E.G. Jr.; Zobel, W.; Stone, G.F.

1976-01-01

TVA has some 21,000 MWe of nuclear generation in various phases of design, construction, or operation. When Browns Ferry was designed in the late 1960's, there were no guidelines available regarding implant radiation control features, so TVA relied on good engineering and health physics judgement in developing its design and operating criteria for radiation protection. After two years of operation at Browns Ferry, the authors experience shows that their design criteria were in most cases adequate or more than adequate. However, several areas present continuing problems relative to radiation and contamination control. In view of the recent NRC ALARA guidelines, they have instituted a program to ensure that the ALARA concept is made an integral part of their design and operating plans. Administrative documents were issued giving management support to the ALARA concept. A 4-member management audit team consisting of representatives from their design, operating, and radiation protection groups was established to review the effectiveness of radiation protection design features and operating activities on a plant-by-plant basis. Reports and recommendations from these audits are sent to top-level management staff. Their goal is to maintain an audit-appraisal system consisting of in-plant awareness of radiation and contamination conditions, assessment of trends in occupational radiation exposures, and feedback to their designers regarding problems encountered during operation and maintenance activities

Report on the BWR owners group radiation protection/ALARA Committee

International Nuclear Information System (INIS)

Aldrich, L.R.

1995-01-01

Radiation protection programs at U.S. boiling water reactor (BWR) stations have evolved during the 1980s and early 1990s from a regulatory adherence-based endeavor to a proactive, risk-based radiation protection and prevention mission. The objectives are no longer to merely monitor and document exposure to radiation and radioactive materials. The focus of the current programs is the optimization of radiation protection of occupational workers consistent with the purpose of producing cost-effective electric power. The newly revised 10 CFR 20 defines the term ALARA (as low as reasonably achievable) to take into account the state of technology, the economics of improvements in relation to the state of the technology, and the benefits to the public health and safety. The BWR Owners Group (BWROG) initially formed the Radiation Protection/ALARA Committee in January 1990 to evaluate methods of reducing occupational radiation exposure during refueling outages. Currently, twenty U.S. BWR owner/operators (representing 36 of the operational 37 domestic BWR units), as well as three foreign BWR operators (associate members), have broadened the scope to promote information exchange between BWR radiation protection professionals and develop good practices which will affect optimization of their radiation protection programs. In search of excellence and the challenge of becoming open-quotes World Classclose quotes performers in radiation protection, the BWROG Radiation Protection/ALARA Committee has recently accepted a role in assisting the member utilities in improving radiation protection performance in a cost-effective manner. This paper will summarize the recent activities of this Committee undertaken to execute their role of exchanging information in pursuit of optimizing the improvement of their collective radiation protection performance

Report on the BWR owners group radiation protection/ALARA Committee

Energy Technology Data Exchange (ETDEWEB)

Aldrich, L.R. [Commonwealth Edison Co., Downers Grove, IL (United States)

1995-03-01

Radiation protection programs at U.S. boiling water reactor (BWR) stations have evolved during the 1980s and early 1990s from a regulatory adherence-based endeavor to a proactive, risk-based radiation protection and prevention mission. The objectives are no longer to merely monitor and document exposure to radiation and radioactive materials. The focus of the current programs is the optimization of radiation protection of occupational workers consistent with the purpose of producing cost-effective electric power. The newly revised 10 CFR 20 defines the term ALARA (as low as reasonably achievable) to take into account the state of technology, the economics of improvements in relation to the state of the technology, and the benefits to the public health and safety. The BWR Owners Group (BWROG) initially formed the Radiation Protection/ALARA Committee in January 1990 to evaluate methods of reducing occupational radiation exposure during refueling outages. Currently, twenty U.S. BWR owner/operators (representing 36 of the operational 37 domestic BWR units), as well as three foreign BWR operators (associate members), have broadened the scope to promote information exchange between BWR radiation protection professionals and develop good practices which will affect optimization of their radiation protection programs. In search of excellence and the challenge of becoming {open_quotes}World Class{close_quotes} performers in radiation protection, the BWROG Radiation Protection/ALARA Committee has recently accepted a role in assisting the member utilities in improving radiation protection performance in a cost-effective manner. This paper will summarize the recent activities of this Committee undertaken to execute their role of exchanging information in pursuit of optimizing the improvement of their collective radiation protection performance.

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Kaurin, D.G.; Khan, T.A.; Sullivan, S.G.; Baum, J.W.

1993-07-01

The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in the continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This is volume 7 of the series. The abstracts in this bibliography were selected from proceedings of technical meetings and conferences, journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to radiation protection and dose reduction, and ranges from use of robotics to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 7 contains 293 abstract, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 7. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes

ALARA database value in future outage work planning and dose management

International Nuclear Information System (INIS)

Miller, D.W.; Green, W.H.

1995-01-01

ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system's ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed

ALARA database value in future outage work planning and dose management

Energy Technology Data Exchange (ETDEWEB)

Miller, D.W.; Green, W.H. [Clinton Power Station Illinois Power Co., IL (United States)

1995-03-01

ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system`s ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed.

ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Amendment 1 for Appendix B: Install flex-pipe on tank riser spools

International Nuclear Information System (INIS)

1998-01-01

This amendment to Appendix B contains the specific ALARA evaluations for installing flex-pipe on riser spools to accommodate ventilation duct connections to the north risers of each tank. The work will be a routine task that is part of the Equipment Installation and Mobilization phase of the project. The dose rates were estimated using the recent Radiological Surveillance Section radiological survey: SAAS-97-063S. Task B-6 has been added to the OHF Project ALARA review process to address a field decision to modify an approach to installing the tank ventilation system. The revised approach will incorporate 12-in. diameter, 36-in. long, stainless steel flex-pipe connected to each north riser spool to address the problem of pipe fitting multiple bends and turns expected with the 12-in. PVC duct. This improved approach will reduce the time necessary to install the duct system between the tanks and the ventilation skid. However, the task includes opening the 12-in. riser spool connections to replace the currently installed blind gaskets. Since a riser spool for each tank will be opened, there is a potential for significant personnel exposure and spread of contamination that will addressed through this ALARA review process

The program of the ALARA Center at Brookhaven National Laboratory

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.

1993-01-01

In 1984 the Brookhaven National Laboratory was asked by the Nuclear Regulatory Commission to set up a Center to monitor dose-reduction efforts in the US and abroad and to focus the industry's attention on ALARA. The paper summarizes the main work of the ALARA Center between 1984 and 1992. The Center maintains nine data bases for the NRC and the Nuclear Power Industry. These databases are constantly updated and access to them is provided through a personal computer and a modem and by periodic publications in the form of a newsletter and NUREG reports. Also described briefly are eight other projects related to dose-reduction at nuclear power plants that the Center has carried out for the NRC. Among these are projects that analyze the cost-effectiveness of engineering modifications, look at worldwide activities at dose reduction and compare US and foreign dose experience, examine high-dose worker groups and high-dose jobs, develop optimum techniques to control contamination at nuclear plants, and look at the doses being received by men and women in all sectors of the nuclear industry

Can practical ALARA be taught?

International Nuclear Information System (INIS)

Guest, R. Monty

2008-01-01

Full text: Purpose: Outside of the nuclear industry, many users of sources of ionising radiation may be characterised as 'High Frequency/Low Dose' users. It is argued here that they have special training requirements in order to understand the ICRP concept ALARA, indeed all the fundamental concepts of radiological protection and their relevance to the workplace. It is not practicable to practise dose avoidance in many situations so dose reduction becomes even more important. For example, laboratory life sciences researchers often have to use very small quantities and activities of beta emitting radioisotopes which give small or minuscule external doses to well trained workers but can give extremely serious high doses if mishandled Similarly, dentists routinely use 60- 100 kV X-ray generators to diagnose abnormalities and disease which other techniques would fail to detect. By practising simple and effective dose reduction methods, they can reduce the dose to themselves and their patients to arguably trivial levels. Method: The paper will use examples from Radiation Protection Supervisors courses run over the past 6 years for UK pharmaceutical companies and research into courses for general dental practitioners run over the past 8 years in East Anglia, England. The latter courses must meet the requirements laid down in the Ionising Radiation (Medical Exposure) Regulations 2000 and the requirements of the professional dental association, the British Dental Council, and the continuing professional development requirements of the dental registration body, the General Dental Council. Major Findings and Conclusions: The research findings show an urgent need to train dental practitioners in the concepts and practical aspects of dose avoidance and dose minimisation, social and economic factors being considered. Pharmaceutical company research Radiation Protection Supervisors are generally well trained but also need to know the practical implications of the ALARA principle

Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

International Nuclear Information System (INIS)

Khan, T.A.; Roecklein, A.K.

1995-03-01

This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately

Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States); Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications

1995-03-01

This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

Experience of ALARA in controlling radiocaesium discharges to the Irish Sea

International Nuclear Information System (INIS)

Hunt, G.J.

1984-01-01

Radiocaesium discharges to the Irish Sea, which primarily originate from corrosion of magnox fuel in the Sellafield storage ponds, are a source of public radiation exposure mainly through the fish and shellfish consumption pathway. Experience of ALARA in the context of reducing these discharges is described. The operators, British Nuclear Fuels Limited (BNFL), in consultation with Government Departments, decided to install an ion exchange plant to remove radioactivity from pond effluents. This plant is scheduled for commissioning in 1984 and optimisation will play a major part in determining its operating regime. Meanwhile, measures have been taken to reduce discharges using skips of zeolite installed in the ponds. Experience of ALARA in determining the optimum replacement rate of skips is described. A major consideration was differential cost-benefit analysis. Following installation of skips at the rate thereby indicated, discharges are being reduced by about half. A further major reduction is expected when the ion exchange plant becomes available. (author)

Radiation protection-culture. Culture improvement in radiation protection and ALARA behaviour

International Nuclear Information System (INIS)

Boehler, M.C.

1994-12-01

In order to that the optimization principle become an actual professional liable dynamical critter in the radiological protection topics, the hierarchic impulse and the personnel sensitiveness are determining. The ALARA (As Low As Reasonably Achievable) in the firm cultivation modify the behaviour and act philosophy. 7 refs., 2 figs

Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel; Proposition d'organisation et procedure ALARA pour le suivi et le retour d'experience des chantiers de maintenance: application au RGV

Energy Technology Data Exchange (ETDEWEB)

Lochard, Jacques; Lefaure, Christian

1989-12-01

This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example.

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 7

Energy Technology Data Exchange (ETDEWEB)

Kaurin, D.G.; Khan, T.A.; Sullivan, S.G.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1993-07-01

The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in the continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This is volume 7 of the series. The abstracts in this bibliography were selected from proceedings of technical meetings and conferences, journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to radiation protection and dose reduction, and ranges from use of robotics to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 7 contains 293 abstract, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 7. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes.

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 8

Energy Technology Data Exchange (ETDEWEB)

Sullivan, S.G.; Khan, T.A.; Xie, J.W. [Brookhaven National Lab., Upton, NY (United States)

1995-05-01

The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in a continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This volume 8 of the series. The abstracts in this bibliography were selected form proceedings of technical meetings and conference journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to the many aspects of radiation protection and dose reduction, and ranges form use of robotics, to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 8 contains 232 abstracts, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 8. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes.

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 8

International Nuclear Information System (INIS)

Sullivan, S.G.; Khan, T.A.; Xie, J.W.

1995-05-01

The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in a continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This volume 8 of the series. The abstracts in this bibliography were selected form proceedings of technical meetings and conference journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to the many aspects of radiation protection and dose reduction, and ranges form use of robotics, to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 8 contains 232 abstracts, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 8. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Sullivan, S.G.; Baum, J.W.

1993-12-01

This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and aocelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts. An author index and a subject index are provided to facilitate use. Both indices contain the abstract numbers from previous volumes, as well as the current volume. Information that the reader feels might be included in the next volume of this bibliography should be submitted to the BNL ALARA Center.

Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel; Proposition d'organisation et procedure ALARA pour la preparation le suivi et le retour d'experience des chantiers de maintenance: application au RGV

Energy Technology Data Exchange (ETDEWEB)

Lochard, Jacques; Lefaure, Christian

1990-01-01

This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example.

ALARA ASSESSMENT OF SETTLER SLUDGE SAMPLING METHODS

International Nuclear Information System (INIS)

Nelsen, L.A.

2009-01-01

The purpose of this assessment is to compare underwater and above water settler sludge sampling methods to determine if the added cost for underwater sampling for the sole purpose of worker dose reductions is justified. Initial planning for sludge sampling included container, settler and knock-out-pot (KOP) sampling. Due to the significantly higher dose consequence of KOP sludge, a decision was made to sample KOP underwater to achieve worker dose reductions. Additionally, initial plans were to utilize the underwater sampling apparatus for settler sludge. Since there are no longer plans to sample KOP sludge, the decision for underwater sampling for settler sludge needs to be revisited. The present sampling plan calls for spending an estimated $2,500,000 to design and construct a new underwater sampling system (per A21 C-PL-001 RevOE). This evaluation will compare and contrast the present method of above water sampling to the underwater method that is planned by the Sludge Treatment Project (STP) and determine if settler samples can be taken using the existing sampling cart (with potentially minor modifications) while maintaining doses to workers As Low As Reasonably Achievable (ALARA) and eliminate the need for costly redesigns, testing and personnel retraining

ALARA ASSESSMENT OF SETTLER SLUDGE SAMPLING METHODS

Energy Technology Data Exchange (ETDEWEB)

NELSEN LA

2009-01-30

The purpose of this assessment is to compare underwater and above water settler sludge sampling methods to determine if the added cost for underwater sampling for the sole purpose of worker dose reductions is justified. Initial planning for sludge sampling included container, settler and knock-out-pot (KOP) sampling. Due to the significantly higher dose consequence of KOP sludge, a decision was made to sample KOP underwater to achieve worker dose reductions. Additionally, initial plans were to utilize the underwater sampling apparatus for settler sludge. Since there are no longer plans to sample KOP sludge, the decision for underwater sampling for settler sludge needs to be revisited. The present sampling plan calls for spending an estimated $2,500,000 to design and construct a new underwater sampling system (per A21 C-PL-001 RevOE). This evaluation will compare and contrast the present method of above water sampling to the underwater method that is planned by the Sludge Treatment Project (STP) and determine if settler samples can be taken using the existing sampling cart (with potentially minor modifications) while maintaining doses to workers As Low As Reasonably Achievable (ALARA) and eliminate the need for costly redesigns, testing and personnel retraining.

Alara - from theory towards practice

International Nuclear Information System (INIS)

Lochard, J.; Lombard, J.; Stokell, P.J.; Croft, J.R.

1991-01-01

The Alara principle states that all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account. It is a simple concept - the idea behind it is widely used in nearly all spheres of life, i.e. to do the best one can under the given circumstances. This book aims to help define what is meant by best in the context of radiation protection. It describes a procedure that is useful in structuring one's approach to any particular situation where a decision as to the best course of action is required. It also provides practical guidance on how the concept can be incorporated into radiation protection programmes. This book has been written as a reference manual on both the theoretical and practical aspects of the subject. But it is especially targeted at those involved in radiation protection at the practical level

Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel

International Nuclear Information System (INIS)

Lochard, Jacques; Lefaure, Christian

1990-01-01

This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example

Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel

International Nuclear Information System (INIS)

Lochard, Jacques; Lefaure, Christian

1989-12-01

This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example

CSER 95-002: ALARA shielding for IAEA SNM container movement

International Nuclear Information System (INIS)

Miller, E.M.

1995-01-01

This CSER qualifies use of a 5% borated, lead foil lined polyethylene 1 inch annulus as a bucket and in a small carrier to move sealed containers of plutonium. The containers are Oversize Cans or smaller containing plutonium limited in mass and H/Pu ratio by PFP storage and transportation CPS's. These ALARA shielding units reduce personnel exposure to the radiation from the containers as they are moved for assay and other required activities

ALARA principle - new philosophy in radiation therapy of papillary thyroid carcinoma

International Nuclear Information System (INIS)

Hadjieva, T.

2003-01-01

The papillary thyroid carcinoma is a model for a successful multidisciplinary oncological therapy with the early stage survival similar to that for normal population. The iodine radiotherapy is a part of the complex treatment leading to these results. The radiation protection principle ALARA is created for healthy people. The authors have formulated it for the purposes of radiotherapy and have built in, as a basic philosophy, in the new radiotherapy concept. It has increased the benefit:risk ratio for the patient. In this case ALARA means: reduction of the indications for treatment with 131 I in the early stages of papillary carcinoma; achievement of tumor control with minimal possible activity in advanced cases; medicamentous, dietary and other measures, reducing the dose burden during and after the treatment, extension of the overall treatment period through a control of the tumor marker thyroglobulin; special treatment and diagnostic regime for children and adolescents, a minimum radiation invasive and economically and socially adequate algorithm for the long-time follow-up of the patients. This ensures a high life quality for the healed patients, comparable with that of the other people

Electricite de France`s ALARA policy

Energy Technology Data Exchange (ETDEWEB)

Stricker, L. [EDF - DEPT, Paris la Defense (France); Rollin, P. [EDF Radioprotection Committee, Paris (France)

1995-03-01

In 1992, Electricite de France - EDF decided to improve the degree to which radiological protection is incorporated in overall management of the utility and set itself the objective of ensuring the same level of protection for workers from contractors as for those from EDF. This decision was taken in a context marked by a deterioration in exposure figures for French plants and by the new recommendations issued by the ICRP. This document describes the policy adopted by EDF at both corporate and plant level to meet these objectives, by: (1) setting up management systems which were responsive but not cumbersome; (2) a broad policy of motivation; (3) the development and use of suitable tools. The document then describes some quite positive results of EDF`s ALARA policy, giving concrete examples and analyzing the changes in global indicators.

Cost-effectiveness studies as part of an ALARA program

International Nuclear Information System (INIS)

Baum, J.W.

1986-01-01

Recent studies of cost effectiveness of engineering modifications for dose reduction at nuclear power plants conducted at BNL will be considered in this report. Since each of these items has the potential for a 50% to 60% reduction in collective dose, it appears there is large potential for dose reduction from engineering type modifications. The question that must be answered for each plant is ''which modifications or improvements are required for optimization (ALARA). The purpose of this paper is to illustrate that quantified optimization need not be costly and can often be highly beneficial

Lessons learned in planning ALARA/health physics support for major nuclear power plant outages

International Nuclear Information System (INIS)

Gilman, T.R.; Lesinski, M.L.

1987-01-01

Although as low as reasonably achievable (ALARA)/health physics is viewed as necessary support for nuclear power plant outage work, it can be the last area to which attention is given in preparing for a large-scope outage. Inadequate lead times cause last-minute preparations resulting in delays in planned work. The Dresden Unit 3 Recirculation Piping Replacement Project is examined from a planning viewpoint. The attention that was given the various areas of a comprehensive ALARA/health physics program is examined, and approximate recommended lead times are discussed. The discussion will follow a chronological path from project inception to the beginning stages of outage work. Initially, the scope of work needs to be assessed by individuals familiar with similar projects of equivalent magnitude. Those individuals need to be health physics professionals who understand the particular utility and/or the site's way of doing business. They should also possess a good understanding of preferred industry practices

An evaluation of high-dose jobs for ALARA improvement

International Nuclear Information System (INIS)

Mun, J. H.; Kim, H. S.

1997-01-01

It is well known that about 70 percent of occupational dose have incurred from maintenance jobs at outage period. To reduce occupational dose, first, the high-dose jobs at the outage period should be identified and evaluated. For this, the database program is used, which contains the ORE data of reference plants, Kori Units 3 and 4. As a result, it is found that the jobs related to steam generator are the highest dose jobs in terms of collective ORE dose. From the analysis of the job procedures of those jobs, the ALARA improvements are also derived

Status of achievements reached in applying optimization of protection in design and normal operation of nuclear facilities

International Nuclear Information System (INIS)

Lochard, J.; Croft, J.R.

1988-01-01

The increased emphasis in recent years on the ALARA principle and its practical implementation has opened new perspectives in the organisation of radiological protection. This change could be characterised as a shift from an 'a posteriori' control, (i.e. demonstrating that dose limits had not been exceeded), towards an 'a priori' management or dose predictive approach. Undoubtedly in both operation and design conscious efforts are made to achieve ALARA. However, there are certainly differences in various organisations' perceptions of what this practically entails and there is scope for us all to learn. If the 'ALARA Procedure' remains only a tool used at the early stage of design or as an elegant means of justifying past choices, it will have missed its main objective which is to give more rational and coherent management of practical protection at both the design and operational stages. We feel that the integration of the structured approaches of the ALARA Procedure and the ALARA Audit, into radiation protection programmes provides the best way forwad. This would require ALARA studies moving from the province of the 'experts' to the 'practitioners'. This in turn will require us to provide them with the tools to do the job. The methodology is secure but the areas of dose data collection and the costing of detriment need to be addressed further. Similarly, there is perhaps a need for the 'experts' to develop further experience of using the multiattribute and multicriteria techniques for the higher level decisions

Radiation exposure usage accountability and impact with respect to ALAP (ALARA) analysis

International Nuclear Information System (INIS)

Williams, M.C.

1978-01-01

A unique method has been developed for radiation exposure usage accounting at the N Reactor. This method accounts for exposure usage by specific job and working crafts. The accounting system provides information for use in job planning, exposure resource management, and ALAP (ALARA) analysis. It provides justification for ALAP expenditures, documentation of the effectiveness of exposure reduction efforts, and can be used to establish priorities for ALAP efforts

An efficient but little known tool for the application of the ALARA principle: Isoe (information system on occupational exposure) (in French)

International Nuclear Information System (INIS)

Croq, M.; Mundigl, S.; Lazo, T.; D'Ascenzo, L.; Lefaure, C.

2001-01-01

An efficient but little known tool for the application of the ALARA principle: ISOE (Information System on Occupational Exposure). The Information System on Occupational Exposure to ionizing radiation (ISOE) is a program launched by the Nuclear Energy Agency (NEA) in 1992. It was developed to address the needs of nuclear power plants and safety authorities as a comparison and information tool on practices in terms of optimization (ALARA principle), in NEA member countries. To date, more than 90% of the operating nuclear power plants in the world are participating in this program, which is organized in a decentralized form, with a steering group and four technical centers (Europe, Asia, north America and IAEA). The ISOE program includes an occupational exposure database and an information exchange and communication network. The databases permit the preparation of studies and comparisons of practices, either in a factual or analytical way. Thus, the ISOE program favors exchanges to the benefit of all participants and helps to bring operational radiation protection ever closer towards the 'achievable' of ALARA. (author)

Health physics experiences in achieving ALARA exposures to plant personnel at NAPS

International Nuclear Information System (INIS)

Ramakrishna, V.; Lal Chand

2000-01-01

Unit 1 of NAPS achieved first criticality on 12.3.1989 and Unit 2 achieved on 24.10.1991. Till the end of Feb-2000 these units have completed 1890 and 1811 full power days respectively. The performance of NAPS was expected to be better than the earlier Indian reactors in respect of safe production as well as cumulative radiation exposures. This is because of the major design improvements like: fully double containment system, elimination of 41 Ar by introducing light water in calandria vault, reduction of core based fuel failure rate, separation of high radiation equipment to no occupancy areas during normal operation, a separate purification building for the purification of both moderator and PHT systems, a better layout of equipment and plant areas, elimination of unnecessary equipment in various systems besides ensuring the reliability of equipment for safe operation, selection of materials with low corrosion and activation characteristics etc. In this paper, the operational health physics experiences at NAPS to achieve ALARA exposures to plant personnel are described briefly. (author)

A corporative ALARA engineering support for all EDF sites a major improvement: the generic work areas optimization studies

International Nuclear Information System (INIS)

Quiot, A.; Lebeau, J.

2005-01-01

ALARA studies performed by EDF plants are quite simple and empirical. Most often, feedback experience and common sense, with the help of simple calculations allow reaching useful and efficient decisions. This is particularly the case when the exposure situations are not complex, within a simple environment and with a single source, or one major source. However, in more complex cases this is not enough to guarantee that actual ALARA solutions are implemented. EDF has then decided to use its national corporate engineering as a support for its sites. That engineering support is in charge of using very efficient tools such as PANTHER-RP. The objective of the presentation is to describe the engineering process and tools now available at EDF, to illustrate them with a few case studies and to describe the goals and procedures set up by EDF. (authors)

A corporate ALARA engineering support for all EDF sites. A major improvement: the generic work areas optimisation studies

Energy Technology Data Exchange (ETDEWEB)

Quiot, Alain [EDF, SPT, UTO, Le Central, Bat. 420, BP 129, 93162 Noisy-le-Grand Cedex (France); Lebeau, Jacques [Electricite de France, ALARA Project, Site Cap Ampere, 1, place Pleyel, 93282 Saint Denis Cedex (France)

2004-07-01

ALARA studies performed by EDF plants are quite simple and empirical. Most often, feedback experience and common sense, with the help of simple calculations allow reaching useful and efficient decisions. This is particularly the case when the exposure situations are not complex, within a simple environment and with a single source, or one major source. However, in more complex cases this is not enough to guarantee that actual ALARA solutions are implemented. EDF has then decided to use its national corporate engineering as a support for its sites. That engineering support is in charge of using very efficient tools such as PANTHER-RP. The objective of the presentation is to describe the engineering process and tools now available at EDF, to illustrate them with a few case studies and to describe the goals and procedures set up by EDF. (authors)

Cone-beam computed tomography: Time to move from ALARA to ALADA

Energy Technology Data Exchange (ETDEWEB)

Jaju, Prashant P.; Jaju, Sushma P. [Rishiraj College of Dental Sciences and Research Centre, Bhopa(Indonesia)

2015-12-15

Cone-beam computed tomography (CBCT) is routinely recommended for dental diagnosis and treatment planning. CBCT exposes patients to less radiation than does conventional CT. Still, lack of proper education among dentists and specialists is resulting in improper referral for CBCT. In addition, aiming to generate high-quality images, operators may increase the radiation dose, which can expose the patient to unnecessary risk. This letter advocates appropriate radiation dosing during CBCT to the benefit of both patients and dentists, and supports moving from the concept of 'as low as reasonably achievable' (ALARA) to 'as low as diagnostically acceptable' (ALADA.

Incremental ALARA cost/benefit computer analysis

International Nuclear Information System (INIS)

Hamby, P.

1987-01-01

Commonwealth Edison Company has developed and is testing an enhanced Fortran Computer Program to be used for cost/benefit analysis of Radiation Reduction Projects at its six nuclear power facilities and Corporate Technical Support Groups. This paper describes a Macro-Diven IBM Mainframe Program comprised of two different types of analyses-an Abbreviated Program with fixed costs and base values, and an extended Engineering Version for a detailed, more through and time-consuming approach. The extended engineering version breaks radiation exposure costs down into two components-Health-Related Costs and Replacement Labor Costs. According to user input, the program automatically adjust these two cost components and applies the derivation to company economic analyses such as replacement power costs, carrying charges, debt interest, and capital investment cost. The results from one of more program runs using different parameters may be compared in order to determine the most appropriate ALARA dose reduction technique. Benefits of this particular cost / benefit analysis technique includes flexibility to accommodate a wide range of user data and pre-job preparation, as well as the use of proven and standardized company economic equations

The preliminary success of ALARA implementation in Daya Bay NPP

International Nuclear Information System (INIS)

Yang Maochun; Chen Degan

2000-01-01

Based on the practical condition of the plant and in reference to advanced management experiences worldwide, Daya Bay Nuclear Power Plant has established its own peculiar management system for radiation protection management and ALARA implementation. The characteristics of the system are: radiation protection training to all workers, active involvement of all managers and staffs, and whole process safety control to maintenance activities. The management philosophy of 'workers are responsible for their own radiation safety' is adopted in the plant. A strict, formalized and systematic whole staff radiation protection training, evaluation, authorization and periodically refreshing mechanism had been established and executed in the plant. In the organizational point of view, the responsibilities of line managers were specified in plant procedures, ALARA coordination organization on plant level and for specific activities were established. Meanwhile, the plant highlighted the defining, following up, controlling and advertising of radiation protection targets. All these measures made radiation protection management be the responsibilities of a safety network in which whole staffs are involved. In the practical radiation protection activities, the plant focuses on works of high radiation risk and performs whole process control. In addition, professional radiation protection staff played an important and active role in technical advisory and control of radiation protection. Satisfactory results have been achieved in Daya Bay NPP in radiation protection in the past years. The collective dose including that of contractors per unit and year have been declining from 0.99 man·Sv/Unit·Year in 1995 to 0.667 man·Sv/Unit·Year in 1998, which were consistently lower than the best quartile result of PWR plants in WANO reports each year. Individual dose was also controlled at a very low level, no one was overexposed in the past years

ALARA (As Low As Reasonable Achievable) procedure applied to fuel assembly fabrication with enriched reprocessing uranium (ERU)

International Nuclear Information System (INIS)

Guimaraes, Leonam dos Santos; Degrange, Jean Pierre

1998-01-01

The study introduced by this paper compose the first step to the implementation of ALARA (As Low As Reasonable Achievable) for a nuclear fuel assembly factory which one of its two production lines will be designed to work with Enriched Reprocessing Uranium (ERU). This step includes the reference situation analysis is based on previsional dosimetric evaluations for individual and collective exposures of each factory operator (117 in total) working on 7 work stations, considering 6 annual production scenarios (10, 50 75, 100 and 150 ERU tons), which corresponds to an annual production of 600 tons (ERU plus enriched natural uranium ENU). The exposure indicators evolution, expressed in terms of collective dose, annual individual dose and radiological detrimental cost for workers, is also used in a complimentary way to guide the analysis. (author)

BNL ALARA Center experience with an information exchange system on dose control at nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.; Khan, T.A.

1992-01-01

The essential elements of an international information exchange system on dose control at nuclear power plants are summarized. Information was collected from literature abstracting services, by attending technical meetings, by circulating data collection forms, and through personal contacts. Data are assembled in various databases and periodically disseminated to several hundred interested participants through a variety of publications and at technical meetings. Immediate on-line access to the data is available to participants with modems, commercially available communications software, and a password that is provided by the Brookhaven National Laboratory (BNL) ALARA Center to authorized users of the system. Since January 1992, rapid access also has been provided to persons with fax machines. Some information is available for ''polling'' the BNL system at any time, and other data can be installed for polling on request. Most information disseminated to data has been through publications; however, new protocols, simplified by the ALARA Center staff, and the convenience of fax machines are likely to make the earlier availability of information through these mechanisms increasingly important

ALARA and decommissioning: The Fort St. Vrain experience

Energy Technology Data Exchange (ETDEWEB)

Borst, T.; Niehoff, M. [Public Service Co. of Colorado, Platteville, CO (United States); Zachary, M. [Scientific Ecology Group, Platteville, CO (United States)

1995-03-01

The Fort St. Vrain Nuclear Generating Station, the first and only commercial High Temperature Gas Cooled Reactor to operate in the United States, completed initial fuel loading in late 1973 and initial startup in early 1974. Due to a series of non-nuclear technical problems, Fort St. Vrain never operated consistently, attaining a lifetime capacity factor of slightly less than 15%. In August of 1989, the decision was made to permanently shut down the plant due to control rod drive and steam generator ring header failures. Public Service Company of Colorado elected to proceed with early dismantlement (DECON) as opposed to SAFSTOR on the bases of perceived societal benefits, rad waste, and exposure considerations, regulatory uncertainties associated with SAFSTOR, and cost. The decommissioning of Fort St. Vrain began in August of 1992, and is scheduled to be completed in early 1996. Decommissioning is being conducted by a team consisting of Westinghouse, MK-Ferguson, and Scientific Ecology Group. Public Service Company of Colorado as the licensee provides contract management and oversight of contractor functions. An aggressive program to maintain project radiation exposures As Low As Reasonably Achievable (ALARA) has been established, with the following program elements: temporary and permanent shielding contamination control; mockup training; engineering controls; worker awareness; integrated work package reviews communication; special instrumentation; video camera usage; robotics application; and project committees. To date, worker exposures have been less than project estimates. from the start of the project through Februrary of 1994, total exposure has been 98.666 person-rem, compared to the project estimate of 433 person-rem and goal of 347 person-rem. The presentation will discuss the site characterization efforts, the radiological performance indicator program, and the final site release survey plans.

Application of ALARA principles to shipment of spent nuclear fuel

International Nuclear Information System (INIS)

Greenborg, J.; Brackenbush, L.W.; Murphy, D.W.; Burnett, R.A.; Lewis, J.R.

1980-05-01

The public exposure from spent fuel shipment is very low. In view of this low exposure and the perfect safety record for spent fuel shipment, existing systems can be considered satisfactory. On the other hand, occupational exposure reduction merits consideration and technology improvement to decrease dose should concentrate on this exposure. Practices that affect the age of spent fuel in shipment and the number of times the fuel must be shipped prior to disposal have the largest impact. A policy to encourage a 5-year spent fuel cooling period prior to shipment coupled with appropriate cask redesign to accommodate larger loads would be consistent with ALARA and economic principles. And finally, bypassing high population density areas will not in general reduce shipment dose

Commissioning of experimental enclosures (Hutches) at the Advanced Photon Source - A to Z ALARA

International Nuclear Information System (INIS)

Vacca, J.; Job, P. K.; Rauchas, A.; Justus, A.; Veluri, V. R.

2000-01-01

The Advanced Photon Source (APS), 7 GeV electron Storage Ring at the Argonne National Laboratory is designed to be a major national user facility providing high-brilliance x-ray beams. Figure 1 shows a plan view of the APS. At completion, APS will have 35 bending magnet (BM) beamlines and 35 insertion device (ID) beamlines. A typical x-ray beamline at APS comprises of a front end (FE) that confines the beam; a first optics enclosure (FOE) which houses optics to filter and monochromatize the beam; and beam transports, additional optics, and the experiment stations. Figure 2 shows a section of the storage ring with the layout of the ID and BM beamlines and typical experiment stations. The first x-ray beam was delivered to an experiment station in 1995. Ever since, to date, over 120 experimental stations (hutches) have been commissioned and are receiving intense x-ray beams of varying energies for various experiments. This paper describes in some detail the steps involved in the process of commissioning experimental stations and the implementation of the ALARA at each step

The ALARA project of the EDF nuclear park exploitation

International Nuclear Information System (INIS)

Potoczek, J.

1998-01-01

To bring the exploitation of the nuclear park of EDF at the level of the best exploiters in the world in matter of collective and individual dosimetry, the ALARA principle coordinates numerous actions: to associate the temporary societies, to define common language, methods and tools for the whole park to organize a level effect in this area, to optimize the maintenance that is expansive in radiation doses, to make the different levels of management responsible on dosimetric stakes, to reduce the singular sources of exposure, to assure the organisation and exploitation of the experience back in this field and adapt consequently the system of information. The results are cheerful and the objectives for 2000 are: less than 1.2 h.Sv by year and by reactor, no intervener whom annual radiation dose is upper than 20 mSv (out of exceptional case). (N.C.)

Status of the ITER tokamak nuclear shielding and radiological protection design

Energy Technology Data Exchange (ETDEWEB)

Leichtle, D., E-mail: dieter.leichtle@f4e.europa.eu [Fusion for Energy, Josep Pla 2, Barcelona 08019 (Spain); Chaffard, P.Y.; Izquierdo, J. [Fusion for Energy, Josep Pla 2, Barcelona 08019 (Spain); Juarez, R. [UNED, Juan del Rosal 12, Madrid 28040 (Spain); Pampin, R.; Portone, A. [Fusion for Energy, Josep Pla 2, Barcelona 08019 (Spain)

2016-11-01

Highlights: • Comprehensive review of design status of the ITER tokamak regarding nuclear shielding. • Investigation of shield design options and streaming mitigation measures. • Review of state-of-the-art shutdown dose rate analyses for selected port systems. - Abstract: Nuclear shielding of the ITER tokamak encompasses several systems and interfaces in a complex radiation environment. Therefore any shielding design has to involve a series of structures, systems and components in an integrated approach. This is evident for the complex ex-vessel radiation environment with streaming and leakage of plasma neutrons and subsequent activation of ex-vessel structures which give raise to excessive shutdown dose rates in accessible areas of the cryostat. The paper reviews recent nuclear analyses related to the performance of primary shields and highlights challenges toward an integrated nuclear shielding design. The general need of propagation of shielding requirements is highlighted in the context of radiation cross talk due to penetrations. Radiation streaming through gaps and penetrations is a key problem in any efficient shield design. The impact on the evolving radiation environment due to several design options along streaming paths such as port gaps, as well as their modeling for nuclear analysis, is presented. Implications regarding design integration and compliance with integrated shielding requirements and ALARA dose are finally given.

Practical application of the ALARA principle in management of the nuclear legacy: optimization under uncertainty

International Nuclear Information System (INIS)

Smith, Graham; Sneve, Malgorzata K.

2008-01-01

Full text: Radiological protection has a long and distinguished history in taking a balanced approach to optimization. Both utilitarian and individual interests and perspectives are addressed through a process of constrained optimisation, with optimisation intended to lead to the most benefit to the most people, and constraints being operative to limit the degree of inequity among the individuals exposed. At least, expressed simplistically, that is what the recommendations on protection are intended to achieve. This paper examines the difficulties in achieving that objective, based on consideration of the active role of optimisation in regulatory supervision of the historic nuclear legacy. This example is chosen because the application of the ALARA principle has important implications for some very major projects whose objective is remediation of existing legacy facilities. But it is also relevant because timely, effective and cost efficient completion of those projects has implications for confidence in the future development of nuclear power and other uses of radioactive materials. It is also an interesting example because legacy management includes mitigation of some major short and long term hazards, but those mitigating measures themselves involve operations with their own risk, cost and benefit profiles. Like any other complex activity, a legacy management project has to be broken down into logistically feasible parts. However, from a regulatory perspective, simultaneous application of ALARA to worker protection, major accident risk mitigation and long-term environmental and human health protection presents its own challenges. Major uncertainties which exacerbate the problem arise from ill-characterised source terms, estimation of the likelihood of unlikely failures in operational processes, and prospective assessment of radiological impacts over many hundreds of years and longer. The projects themselves are set to run over decades, during which time the

Backfitting of the nuclear power plant Borssele. A practical application of the ALARA-principle

International Nuclear Information System (INIS)

Leurs, C.J.

1998-01-01

In two articles an overview is given of the adjustments for the title plant and how the radiation load of employees is kept as low as possible according to the newest insights of the ALARA-principle. In this article attention is paid to the results of the project 'Modifications' which comprises 16 system engineering modifications. The maximum attention for radiation protection resulted in a collective dose of circa 2500 millisievert, which is a factor 4 lower than the first estimation of the radiation load. 7 refs

ALARA beyond dollars per person-rem

International Nuclear Information System (INIS)

Waite, D.; Harper, W.

1983-01-01

The trend in radiological assessments over the past decade is to extract more and more information from each bit of data. In the 1960's it was sufficient to calculate doses to the maximum individual and populations from exposure to critical nuclides in critical pathways. The 1970's brought the UNSCEAR and BEIR Reports and made the extension of calculated doses to predicted health effects fashionable. The 1980's may see data analysis extended still further to the use of an index of lost productivity. Advantages of these types of uses of dose calculations include the derivation of further insight into the system being analyzed and the attainment of a greater measure of comparability with impacts from agents other than radiological. The question is, where does the uncertainty in the analytical result overwhelm any possibility of its usefulness. This presentation addresses this question in the context of a performance analysis of a high-level nuclear waste repository. Estimates of uncertainty in dose calculations, health effects predictions and loss of productivity predictions are derived from examination of the open literature and the use of propagation of uncertainty techniques. The expected values and uncertainties are compounded as they would be in an ALARA analysis and the outcomes are analyzed. The advantages and disadvantages of truncating the analysis at each stage of extension are discussed. 21 references, 3 tables

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA

International Nuclear Information System (INIS)

Dionne, B.J.; Sullivan, S.G.; Baum, J.W.

1993-03-01

This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well other topics, has been included. This volume (Volume 4 of the series) contains 209 abstracts. An author index and a subject index are provided to facilitate use. The subject index contains the abstract numbers from previous volumes, as well as the current volume

Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

International Nuclear Information System (INIS)

Chen Xiaoqiu

2009-01-01

Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

Application of the ALARA principle to individual occupational radiation monitoring

International Nuclear Information System (INIS)

Aleinikov, V.E.

1998-01-01

Routine individual occupational radiation monitoring is necessary to ensure that exposure are kept as low as reasonably achievable (ALARA) and that the authorized dose limits are not exceeded. The type and extend of the monitoring depend on the nature and magnitude of occupational radiation exposure. Optimal choice of the wearing time for individual dosimeters, T, has important consequences for achievement of the individual monitoring objects. The choice of T depends on individual dose distribution, the lower detection limit for the detector used, the lost of an information during period of monitoring, the cost of the measurements and the benefits associated with the results. The paper describes the application of quantitative optimization techniques to optimize the wearing time for individual dosimeters. It was shown how optimal wearing time for individual dosimeters depends on dose distribution, the lower detection limit, dose limit, fading and cost of the measurements. (author)

ETF interim design review

International Nuclear Information System (INIS)

Steiner, D.; Rutherford, P.H.

1980-01-01

A three-day ETF Interim Design Review was conducted on July 23-25, 1980, at the Sheraton Potomac Inn in Rockville, Maryland. The intent of the review was to provide a forum for an in-depth assessment and critique of all facets of the ETF design by members of the fusion community. The review began with an opening plenary session at which an overview of the ETF design was presented by D. Steiner, manager of the ETF Design Center, complemented by a physics overview by P.H. Rutherford, chairman of the ETF/INTOR Physics Committee. This was followed by six concurrent review sessions over the next day and a half. The review closed with a plenary session at which the Design Review Board presented its findings. This document consists of the viewgraphs for the opening plenary session and an edited version of the presentations made by Steiner and Rutherford

Use of computerized, 3-dimensional solids modeling and data base management to support radiation mapping and ALARA planning

International Nuclear Information System (INIS)

Schauss, R.D.; Slobodien, M.S.

1986-01-01

The RADiation Mapping and ALARA Planning System (RADMAPS) under development by GPU Nuclear Corporation in conjunction with Construction Systems Associates, Inc., integrates computerized solids modeling and data base management to provide an automated, integrated systems solution to the problems associated with acquiring, managing, and communicating plant radiological data at nuclear facilities. This presentation describes the status of the RADMAPS development and outlines plans for future expansion

Occupational radiation dose assessment for a non site specific spent fuel storage facility

International Nuclear Information System (INIS)

Hadley, J.; Eble, R.G. Jr.

1997-01-01

To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC's). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR's; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab

ALARA and de minimis concepts in regulation of personnel exposure

International Nuclear Information System (INIS)

Baum, J.W.

1987-01-01

The ALARA process should not be limited by a de minimis level on either collective or individual dose, but should be limited or defined by an acceptable discount-rate on future costs and effects, and a monetary value for detriment, to be used in cost-effectiveness or cost-benefit calculations at dose levels well below the regulatory limits. This approach would provide the desired benefit of simplifying the decision process, it makes it more cost effective, and would avoid the inconsistencies of limits on only one of the four parameters of importance in the optimization process. These are average individual effective dose equivalent rate, number of individuals to be included in the summation, years of exposure, and costs, which include costs of analysis to reduce the exposure. This approach emphasizes that these doses to an individual may not be considered trivial by society when given to a very large population, especially if they could easily be avoided. 32 refs., 2 tabs

Application of ALARA to transport of Radio-Isotopes for Medical use

International Nuclear Information System (INIS)

Fett, H. J.; Lange, F.; Schwarz, G.; Van Hienen, J. F. A.; Jansma, R.; Gelder, R.; Shaw, K. B.; Gulberg, O.; Josefsson, D.; Svahn, B.

2002-01-01

In 1999 a multi-national research project on transport safety commissioned by DG-TREN of the European Commission was completed and reported in The Evaluation of the Situation in the EC as regards Safety in the Transport of Radioactive Material and the Prospects for the Development of such Type of Transport (EC Contract No 4.1020/D/97-003. The result project was focussed on the radiological protection for routine (incident-free) shipments of radioactive material (RAM) in the public domain in four EU Member States Germany, the Netherlands, Sweden and the UK. This information satisfies the requirements of the Euratom Basic Safety Standards, Article 14, which calls for reasonable steps taken by EU Member States to ensure and to substantiate that the contribution to exposure from practices including transport operations involving radioactive substances, is kept as low as reasonably achievable (ALARA), economic and social factors being taken into account. The present paper, which has been partially based on the 1999 study for the European Commission, is focussed on the application of ALARA to the shipments by road in the four countries of radioactive material used for health care, research and industry. From the analysis of the data for these shipment it has been found that these shipments result in transport worker effective doses that vary from very low values which represent a major fraction of the applicable dose limit of 20 mSv/yr. From the primarily recorded worker radiation doses collected at the national level indicate, however, that the vast majority of transport workers, i. e. drivers and handlers, receive typically annual effective doses in the range of up to 10 mSv/yr with most values being in the low dose range. The maximum recorded occupational doses of workers involved primarily in manual handling, sorting and moving of high-T1 multiple-package radioisotope shipments at depots, re-distribution centres etc. were found to be from about 10-14 mSv/yr, From the

Design review report for the hydrogen interlock preliminary design

International Nuclear Information System (INIS)

Corbett, J.E.

1996-01-01

This report documents the completion of a preliminary design review for the hydrogen interlock. The hydrogen interlock, a proposed addition to the Rotary Mode Core Sampling (RMCS) system portable exhauster, is intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to validate basic design assumptions and concepts to support a path forward leading to a final design. The conclusion reached by the review committee was that the design was acceptable and efforts should continue toward a final design review

International Peer Reviews of Design Basis

International Nuclear Information System (INIS)

Hughes, Peter

2013-01-01

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

Effect of design improvements on ALARA exposures in PHWRs

International Nuclear Information System (INIS)

Nair, S.N.; Mohandas, P.V.; Gupta, Ashok; Hussain, S.A.

2000-01-01

Design improvements in Indian PHWRs over last thirty years have remarkably reduced the occupational and public exposures. Some of the radiologically offending systems were altogether changed, equipment was judiciously relocated and at component level reduction in number and improvement in quality was carried out. As a result the collective occupational exposures could be brought down by a factor of about 4-5 and average public exposure by a factor of about 10. Since the design improvements are continuous ongoing processes further reduction in exposure will be definitely brought in the coming years. (author)

FDH radiological design review guidelines

International Nuclear Information System (INIS)

Millsap, W.J.

1998-01-01

These guidelines discuss in more detail the radiological design review process used by the Project Hanford Management Contractors as described in HNF-PRO-1622, Radiological Design Review Process. They are intended to supplement the procedure by providing background information on the design review process and providing a ready source of information to design reviewers. The guidelines are not intended to contain all the information in the procedure, but at points, in order to maintain continuity, they contain some of the same information

FDH radiological design review guidelines

Energy Technology Data Exchange (ETDEWEB)

Millsap, W.J.

1998-09-29

These guidelines discuss in more detail the radiological design review process used by the Project Hanford Management Contractors as described in HNF-PRO-1622, Radiological Design Review Process. They are intended to supplement the procedure by providing background information on the design review process and providing a ready source of information to design reviewers. The guidelines are not intended to contain all the information in the procedure, but at points, in order to maintain continuity, they contain some of the same information.

Design reviews from a regulatory perspective

International Nuclear Information System (INIS)

Foster, B.D.

1991-01-01

This paper presents views on the role of the licensing engineer in the design process with specific emphasis on design reviews and the automated information management tools that support design reviews. The licensing engineer is seen as an important member of a design review team. The initial focus of the licensing engineer during design reviews is shown to be on ensuring that applicable regulatory requirements are addressed by the design. The utility of an automated tool, such as a commitments management system, to support regulatory requirements identification is discussed. The next responsibility of the licensing engineer is seen as verifying that regulatory requirements are transformed into measurable performance requirements. Performance requirements are shown to provide the basis for developing detailed design review criteria. Licensing engineer input during design reviews is discussed. This input is shown to be especially critical in cases where review findings may impact application of regulatory requirements. The use of automated tools in supporting design reviews is discussed. An information structure is proposed to support design reviews in a regulated environment. This information structure is shown to be useful to activities beyond design reviews. Incorporation of the proposed information structure into the Licensing Support System is proposed

Computer code for quantitative ALARA evaluations

International Nuclear Information System (INIS)

Voilleque, P.G.

1984-01-01

A FORTRAN computer code has been developed to simplify the determination of whether dose reduction actions meet the as low as is reasonably achievable (ALARA) criterion. The calculations are based on the methodology developed for the Atomic Industrial Forum. The code is used for analyses of eight types of dose reduction actions, characterized as follows: reduce dose rate, reduce job frequency, reduce productive working time, reduce crew size, increase administrative dose limit for the task, and increase the workers' time utilization and dose utilization through (a) improved working conditions, (b) basic skill training, or (c) refresher training for special skills. For each type of action, two analysis modes are available. The first is a generic analysis in which the program computes potential benefits (in dollars) for a range of possible improvements, e.g., for a range of lower dose rates. Generic analyses are most useful in the planning stage and for evaluating the general feasibility of alternative approaches. The second is a specific analysis in which the potential annual benefits of a specific level of improvement and the annual implementation cost are compared. The potential benefits reflect savings in operational and societal costs that can be realized if occupational radiation doses are reduced. Because the potential benefits depend upon many variables which characterize the job, the workplace, and the workers, there is no unique relationship between the potential dollar savings and the dose savings. The computer code permits rapid quantitative analyses of alternatives and is a tool that supplements the health physicist's professional judgment. The program output provides a rational basis for decision-making and a record of the assumptions employed

Managing the radiological risk: ALARA, a principle, an obligation, a state of mind

International Nuclear Information System (INIS)

Lefaure, C.

1995-01-01

According to the 1993 data published by French nuclear operators and by the Ionizing Radiations Protection Office (OPRI), only two workers have exceeded the maximum annual permissible dose of 50 mSv. However, the respect of dose limits is not a sufficient warranty to accept the ionizing radiations exposure risk. The ALARA (As Low As Reasonably Achievable) principle is a masterpiece of the radiological protection system. Its goal is to maintain the exposures as low as reasonably achievable taking into account the socio-economical constraints. In France, the application of this principle is as compulsory as the respect of dose limits. The proper management and optimization of radiological risk requires the motivation of everybody. (J.S.). 2 refs., 3 figs

ALARA efforts in nordic BWRs

Energy Technology Data Exchange (ETDEWEB)

Ingemansson, T.; Lundgren, K.; Elkert, J. [ABB Atom, Vaesteraes (Sweden)

1995-03-01

Some ALARA-related ABB Atom projects are currently under investigation. One of the projects has been ordered by the Swedish Radiation Protection Institute, and two others by the Nordic BWR utilities. The ultimate objective of the projects is to identify and develop methods to significantly decrease the future exposure levels in the Nordic BWRS. As 85% to 90% of the gamma radiation field in the Nordic BWRs originates from Co-60, the only way to significantly decrease the radiation doses is to effect Co and Co-60. The strategy to do this is to map the Co sources and estimate the source strength of Co from these sources, and to study the possibility to affect the release of Co-60 from the core surfaces and the uptake on system surfaces. Preliminary results indicate that corrosion/erosion of a relatively small number of Stellite-coated valves and/or dust from grinding of Stellite valves may significantly contribute to the Co input to the reactors. This can be seen from a high measured Co/Ni ratio in the feedwater and in the reactor water. If stainless steel is the only source of Co, the Co/Ni ratio would be less than 0.02 as the Co content in the steel is less than 0.2%. The Co/Ni ratio in the reactor water, however, is higher than 0.1, indicating that the major fraction of the Co originates from Stellite-coated valves. There are also other possible explanations for an increase of the radiation fields. The Co-60 inventory on the core surfaces increases approximately as the square of the burn-up level. If the burn-up is increased from 35 to 5 MWd/kgU, the Co-60 inventory on the core surfaces will be doubled. Also the effect on the behavior of Co-60 of different water chemistry and materials conditions is being investigated. Examples of areas studied are Fe and Zn injection, pH-control, and different forms of surface pre-treatments.

Use of rank sum method in identifying high occupational dose jobs for ALARA implementation

International Nuclear Information System (INIS)

Cho, Yeong Ho; Kang, Chang Sun

1998-01-01

The cost-effective reduction of occupational radiation exposure (ORE) dose at a nuclear power plant could not be achieved without going through an extensive analysis of accumulated ORE dose data of existing plants. It is necessary to identify what are high ORE jobs for ALARA implementation. In this study, the Rank Sum Method (RSM) is used in identifying high ORE jobs. As a case study, the database of ORE-related maintenance and repair jobs for Kori Units 3 and 4 is used for assessment, and top twenty high ORE jobs are identified. The results are also verified and validated using the Friedman test, and RSM is found to be a very efficient way of analyzing the data. (author)

Excellence in occupational dose reduction in the new millennium: the first international Alara symposium in the 21st century

International Nuclear Information System (INIS)

Martin, A.

2001-01-01

The International Symposium ALARA 2001 on Radiological Protection Challenges in NPP's Management on the Verge of the XXI Century took place in Anaheim. California on February 5-7. In this congress, Anibal Martin, Vice-President of the Consejo de Seguridad Nuclear, received an honorable mention from the Health Physics Society for his professional career in the nuclear arena. After being awarded the commemorative plague, Anibal martin addressed the meeting. His speech is reproduced below. (Author)

Interpretation of ALARA in the Canadian regulatory framework

Energy Technology Data Exchange (ETDEWEB)

Utting, R. [Atomic Energy Control Board, Ottawa, Ontario (Canada)

1995-03-01

The Atomic Energy Control Board (AECB) is responsible for the regulation of all aspects of atomic energy in Canada. This includes the complete nuclear fuel cycle from uranium mining to long-term disposal of nuclear fuel, as well as the medical and industrial utilization of radioisotopes. Clearly, the regulatory approach will differ from practice to practice but, as far as possible, the AECB has attempted to minimize the degree of prescription of regulatory requirements. The traditional modus operandi of the AECB has been to have broad general principles enshrined in regulations with the requirement that licensees submit specific operating policies and procedures to the AECB for approval. In the large nuclear facilities with their sophisticated technical infrastructures, this policy has been largely successful although in a changing legal and political milieu the AECB is finding that a greater degree of proactive regulation is becoming necessary. With the smaller users, the AECB has for a long time found it necessary to have a greater degree of prescription in its regulatory function. Forthcoming General Amendments to the Atomic Energy Control Regulations will, amongst other things, formally incorporate the concept of ALARA into the Canadian regulatory framework. Within the broad range of practices licensed by the AECB it is not practical to provide detailed guidance on optimization that will be relevant and appropriate to all licensees, however the following general principles are proposed.

Effluent Monitoring System Design for the Proton Accelerator Research Center of PEFP

International Nuclear Information System (INIS)

Kim, Jun Yeon; Mun, Kyeong Jun; Cho, Jang Hyung; Jo, Jeong Hee

2010-01-01

Since host site host site was selected Gyeong-ju city in January, 2006. we need design revision of Proton Accelerator research center to reflect on host site characteristics and several conditions. Also the IAC recommended maximization of space utilization and construction cost saving. After GA(General Arrangement) is made a decision, it is necessary to evaluate the radiation analysis of every controlled area in the proton accelerator research center such as accelerator tunnel, Klystron gallery, beam experimental hall, target rooms and ion beam application building to keep dose rate below the ALARA(As Low As Reasonably achievable) objective. Our staff has reviewed and made a shielding design of them. In this paper, According to accelerator operation mode and access conditions based on radiation analysis and shielding design, we made the exhaust system configuration of controlled area in the proton accelerator research center. Also, we installed radiation monitor and set its alarm value for each radiation area

Ecological aspects of the radiation-migration equivalence principle in a closed fuel cycle and its comparative assessment with the ALARA principle

International Nuclear Information System (INIS)

Poluektov, P.P.; Lopatkin, A.V.; Nikipelov, B.V.; Rachkov, V.I.; Sukhanov, L.P.; Voloshin, S.V.

2005-01-01

.e. the ALARA principle. Economic factors are disregarded in constructing the RME principle (for example, the cost of SNF reprocessing to the corresponding depth). However, the RME principle may be demonstrated to broad sections of the public with achieving the necessary understanding, which is of crucial importance. The ALARA principle is not reduced to the RME principle and is a more general programme into which the RME principle may be embedded. The ALARA principle covers all the stages of creating a burial, including the design, building, operation, and closing with the subsequent monitoring. This principle regulates the stages of burial building, the location of waste, the use of remote control and protected equipment for location of waste, environmental control, measures for a decrease in the probability of emergences and their consequences, which should provide the main aim the control and a decrease in the dose load on staff and members of the public at all the stage of creating and operating the RW burial. (author)

New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde; Nuevas recomendaciones del ICRP y el programa ALARA de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Padilla C, I [Comision Federal de Electricidad, Central Laguna Verde (Mexico)

1991-07-01

In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program.

Radiation physics and shielding codes and analyses applied to design-assist and safety analyses of CANDUR and ACRTM reactors

International Nuclear Information System (INIS)

Aydogdu, K.; Boss, C. R.

2006-01-01

This paper discusses the radiation physics and shielding codes and analyses applied in the design of CANDU and ACR reactors. The focus is on the types of analyses undertaken rather than the inputs supplied to the engineering disciplines. Nevertheless, the discussion does show how these analyses contribute to the engineering design. Analyses in radiation physics and shielding can be categorized as either design-assist or safety and licensing (accident) analyses. Many of the analyses undertaken are designated 'design-assist' where the analyses are used to generate recommendations that directly influence plant design. These recommendations are directed at mitigating or reducing the radiation hazard of the nuclear power plant with engineered systems and components. Thus the analyses serve a primary safety function by ensuring the plant can be operated with acceptable radiation hazards to the workers and public. In addition to this role of design assist, radiation physics and shielding codes are also deployed in safety and licensing assessments of the consequences of radioactive releases of gaseous and liquid effluents during normal operation and gaseous effluents following accidents. In the latter category, the final consequences of accident sequences, expressed in terms of radiation dose to members of the public, and inputs to accident analysis, e.g., decay heat in fuel following a loss-of-coolant accident, are also calculated. Another role of the analyses is to demonstrate that the design of the plant satisfies the principle of ALARA (as low as reasonably achievable) radiation doses. This principle is applied throughout the design process to minimize worker and public doses. The principle of ALARA is an inherent part of all design-assist recommendations and safety and licensing assessments. The main focus of an ALARA exercise at the design stage is to minimize the radiation hazards at the source. This exploits material selection and impurity specifications and relies

Formal Design Review Foot Clamp Modification

International Nuclear Information System (INIS)

OTEN, T.C.

2000-01-01

This report documents the Design Review performed for the foot clamp modification. The report documents the acceptability of the design, identifies the documents that were reviewed, the scope of the review and the members of the review team

Advanced Neutron Source radiological design criteria

International Nuclear Information System (INIS)

Westbrook, J.L.

1995-08-01

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

1991 implementation of As Low As Reasonably Achievable (ALARA) administrative radiation exposure levels: Experiences and lessons learned

International Nuclear Information System (INIS)

Aldridge, T.L.; Baumann, B.L.

1993-06-01

As Low As Reasonably Achievable (ALARA) radiation exposure levels were implemented on January 1, 1991, by Westinghouse Hanford Company (WHC), a prime US Department of Energy (DOE) contractor, located in Richland, Washington. This paper describes the radiation exposure levels which were implemented and the associated experiences and lessons learned. The issue of a report from the Committee on Biological Effectiveness of Ionizing Radiation in 1989 prompted DOE to re-evaluate its position on radiation exposure limits and the resulting doses received by occupational radiation workers. DOE requested that all it's contractors determine the impacts to operations from reduced radiation exposure levels

Design review report, 241-S-102 cover plate review; TOPICAL

International Nuclear Information System (INIS)

ADAMS, M.R.

1998-01-01

The design for the cover plate and lead plate for shielding on 241-S-102 was reviewed on 10/21/98. All Review Comment Record comments were resolved to the satisfaction of the reviewers. Additional comments were taken during the meeting and were also resolved. A design calculation for the Radiological Design Review Screening was presented as criteria for the use of 1 inch lead plate. The review concluded that the use of 2 inch steel plate and 1 inch lead plate provided the required safety function required by HNF-SD-WM-810-001, 5.3.2.20, Basis for Interim Operation. The design was approved with the incorporated comments as recorded on RCR's and meeting minutes

Guidelines for control room design reviews

International Nuclear Information System (INIS)

1981-09-01

The control room design review is part of a broad program being undertaken by the nuclear industry and the government to ensure consideration of human factors in nuclear power plant design and operation. The purpose of the control room design review described by these guidelines is to (1) review and evaluate the control room workspace, instrumentation, controls, and other equipment from a human factors engineering point of view that takes into account both system demands and operator capabilities; and (2) to identify, assess, and implement control room design modifications that correct inadequate or unsuitable items. The scope of the control room design review described by these guidelines covers the human engineering review of completed control rooms; i.e., operational control rooms or those at that stage of the licensing process where control room design and equipment selection are committed. These guidelines should also be of use during the design process for new control rooms. However, additional analyses to optimize the allocation of functions to man and machine, and further examination of advanced control system technology, are recommended for new control rooms. Guidelines and references for comprehensive system analyses designed to incorporate human factors considerations into the design and development of new control rooms are presented in Appendix B. Where possible, a generic approach to the control room design review process is encouraged; for example, when control room designs are replicated wholly or in part in two or more units. Even when designs are not replicated exactly, generic reviews which can be modified to account for specific differences in particular control rooms should be considered. Industry organizations and owners groups are encouraged to coordinate joint efforts and share data to develop generic approaches to the design review process. The control room design review should accomplish the following specific objectives. To determine

NFR TRIGA package design review report

International Nuclear Information System (INIS)

Clements, M.D.

1994-01-01

The purpose of this document is to compile, present and document the formal design review of the NRF TRIGA packaging. The contents of this document include: the briefing meeting presentations, package description, design calculations, package review drawings, meeting minutes, action item lists, review comment records, final resolutions, and released drawings. This design review required more than two meeting to resolve comments. Therefore, there are three meeting minutes and two action item lists

Human-system interface design review guideline -- Reviewer`s checklist: Final report. Revision 1, Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.

Optimisation of structural shielding of accelerator control room for compliance with ALARA principle under Indian conditions

International Nuclear Information System (INIS)

Ahmad, Masood; Singh, Brijesh

1999-01-01

The case of a 20 MV x-ray accelerator has been considered in this paper for optimisation. An internationally recommended value of α = US$ 1000 per person-sievert has been assumed. Cost of concrete has been assumed as US$ 82.7/m 3 . It is seen that, extra shielding is needed to satisfy the ALARA principle. Further, the amount of requisite shielding increases with the degree of occupancy and, also, if the local construction materials or the labour are cheaper than considered in this paper. Accordingly 1.5 to 4.75 HVLs may be needed as extra shielding in different situations. Therefore, a site specific and installation specific optimisation of shielding is necessary

Optimization (Alara) and probabilistic exposures: the application of optimization criteria to the control of risks due to exposures of a probabilistic nature

International Nuclear Information System (INIS)

Gonzalez, A.J.

1989-01-01

The paper described the application of the principles of optimization recommended by the International Commission on Radiological Protection (ICRP) to the restrain of radiation risks due to exposures that may or may not be incurred and to which a probability of occurrence can be assigned. After describing the concept of probabilistic exposures, it proposes a basis for a converging policy of control for both certain and probabilistic exposures, namely the dose-risk relationship adopted for radiation protection purposes. On that basis some coherent approaches for dealing with probabilistic exposures, such as the limitation of individual risks, are discussed. The optimization of safety for reducing all risks from probabilistic exposures to as-low-as-reasonably-achievable (ALARA) levels is reviewed in full. The principles of optimization of protection are used as a basic framework and the relevant factors to be taken into account when moving to probabilistic exposures are presented. The paper also reviews the decision-aiding techniques suitable for performing optimization with particular emphasis to the multi-attribute utility-analysis technique. Finally, there is a discussion on some practical application of decision-aiding multi-attribute utility analysis to probabilistic exposures including the use of probabilistic utilities. In its final outlook, the paper emphasizes the need for standardization and solutions to generic problems, if optimization of safety is to be successful

Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA: Volume 4

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.

1989-06-01

This report is the fourth in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory on dose reduction at nuclear power plants. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports and searches of the DOE's Energy Data Base. The abstracts included in this report to operational health physics as well as other subjects which have a bearing on dose reduction at nuclear power plants, such as stress corrosion, cracking, plant chemistry, use of robotics and remote devices, etc. Material on improved design, materials selection, planning and other topics which are related to dose reduction efforts are also included. The report contains 327 abstracts as well as subject and author indices. All information in the current volume is also available from the ALARA Center's bulletin board service which is accessible by personal computers with the help of a modem. The last section of the report explains the features of the bulletin board. The bulletin board will be kept up-to-date with new information and should be of help in keeping people current in the area of dose reduction

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

International Nuclear Information System (INIS)

Dionne, B.J.; Morris, S. III; Baum, J.W.

1998-03-01

The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

Proceedings of an international workshop on historic dose experience and dose reduction (ALARA) at nuclear power plants

International Nuclear Information System (INIS)

Horan, J.R.; Baum, J.W.; Dionne, B.J.

1985-06-01

Dose reduction data and experience from 28 foreign and 10 US nuclear power plants was examined to determine causes for the wide variations in occupational dose from country to country. Major topics discussed were: steam generator and refueling maintenance problems; utility and supplier ALARA programs; effectiveness of dose-reduction modifications; attitudes and training; current and future dose-reduction research. While many parameters contribute to differences of occupational doses between plants from different nations, it is clear that most US plants have higher collective dose equivalent per reactor per megawatt-year than most other countries, even for plants of similar size and age. Worldwide, Finnish and Swedish plants, both PWR and BWR, have achieved the lowest values. Major factors which contribute to low doses include: (1) minimization of cobalt in primary system components exposed to water; (2) careful plant design, layout and component segregation and shielding; (3) plant standardization; (4) selection of components and systems for increased reliability; (5) management interest and commitment; (6) minimum number of workers and in-depth worker training; (7) careful control of primary system oxygen and pH; (8) good primary system water purity to minimize corrosion product formation; (9) use of special tools and robotics; (10) decontamination and passivation of primary systems and components; and (11) extent of backfitting and mandated inspections

Application of the ALARA principle to minimize the collective dose in NPP accident management within the containment

International Nuclear Information System (INIS)

Bogorad, V.; Slepchenko, O.; Kyrylenko, Y.

2016-01-01

The paper focuses on application of the ALARA principle to minimize the collective doses (both for NPP personnel and the public) related to admission of personnel to the containment for accident management activities and depending on operation of ventilation systems. Results from assessment of radiation consequences are applied to a small - break LOCA with failure of LPIS at VVER - 1000 reactors. The public doses are evaluated using up - to - date RODOS, MACCS and HotSpot software for assessment of radiation consequences. The personnel doses are evaluated with MicroShield and InterRAS codes. The time function and optimal value of the collective dose are defined. The developed approach can be applied for minimization of the collective dose for optimization of accident management strategies at NPPs

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

International Nuclear Information System (INIS)

Dionne, B.J.; Morris, S.C. III; Baum, J.W.

1998-01-01

The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report

Lessons Learned at Envirocare of Utah's Containerized Waste Facility (CWF): Dose Minimization Through ALARA Techniques and Tools

International Nuclear Information System (INIS)

Heckman, J.; Gardner, J.; Ledoux, M. R.

2003-01-01

Envirocare of Utah, Inc. (Envirocare) commenced operation of its Class A Containerized Waste Facility (CWF) on October 25, 2001. The opening of this facility began a new era for Envirocare, in that; their core business had always been low level, high volume, bulk radioactive waste. The CWF commenced operations to dispose of low level, low volume, high activity, containerized radioactive waste. Due to the potential for high dose rates on the waste disposal containers, the ALARA principle (As Low As Reasonably Achievable) plays an important role in the operation of the CWF and its mission to properly dispose of waste while minimizing doses to the workers, public, and the environment. This paper will enumerate some of the efforts made by the management and staff of the CWF that have contributed to significant dose reductions

Argon-41 ALARA, or reduction of argon-41 released from the OSTR by use of a nitrogen purging system for the rotating rack facility

International Nuclear Information System (INIS)

Johnson, A.G.; Anderson, T.V.; Dodd, B.; Carpenter, W.T.

1982-01-01

During a generally concurrent era, the NRC began emphasizing the concept of keeping all radiation doses and releases of radioactivity to the environment 'as low as reasonably achievable' (ALARA). In much the same way as the physical security regulations were expanded, the ALARA idea was defined for a number of different NRC licensee categories, but the underlying principle remained the same, namely, reduce occupational doses and releases of radioactivity. In keeping with this NRC policy (i.e., regulatory requirement), the OSTR staff conducted a study of the argon-41 production sites throughout the facility, with the idea of minimizing the production without increasing the potential for higher occupational doses to the staff. The reduction in argon-41 production and release should, after a full year's implementation, result in the 41.68 curie value documented for the past reporting year (July 1, 1980 through June 30, 1981) being cut to about 9 curies per year. This value is based on the fact that the LN purging system was used about the last four months of the stated reporting period. From a dose commitment standpoint, this should reduce the maximum projected annual dose in the unrestricted area under the worst case hypothetical conditions from the currently estimated 1.04 mrem per year to about 0.23 mrem per year

IMPROVED WELL PLUGGING EQUIPMENT AND WASTE MANGEMENT TECHNIQUES EXCEED ALARA GOALS AT THE OAK RIDGE NATIONAL LABORATORY

International Nuclear Information System (INIS)

Whiteside, R.; Pawlowicz, R.; Whitehead, L.; Arnseth, R.

2002-01-01

In 2000, Bechtel Jacobs Company LLC (BJC) contracted Tetra Tech NUS, Inc. (TtNUS) and their sub-contractor, Texas World Operations, Inc. (TWO), to plug and abandon (P and A) 111 wells located in the Melton Valley area of Oak Ridge National Laboratory (ORNL). One hundred and seven of those wells were used to monitor fluid movement and subsurface containment of the low level radioactive liquid waste/grout slurry that was injected into the Pumpkin Valley Shale Formation, underlying ORNL. Four wells were used as hydrofracture injection wells to emplace the waste in the shale formation. Although the practice of hydrofracturing was and is considered by many to pose no threat to human health or the environment, the practice was halted in 1982 after the Federal Underground Injection Control regulations were enacted by United States Environmental Protection Agency (USEPA) making it necessary to properly close the wells. The work is being performed for the United States Department of Energy Oak Ridge Operations (DOE ORO). The project team is using the philosophy of minimum waste generation and the principles of ALARA (As Low As Reasonably Achievable) as key project goals to minimize personnel and equipment exposure, waste generation, and project costs. Achievement of these goals was demonstrated by the introduction of several new pieces of custom designed well plugging and abandonment equipment that were tested and used effectively during field operations. Highlights of the work performed and the equipment used are presented

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

1998-03-01

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

Review of the Tritium Extraction Facility design

International Nuclear Information System (INIS)

Barton, R.W.; Bamdad, F.; Blackman, J.

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the US Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Review of the Tritium Extraction Facility Design

International Nuclear Information System (INIS)

Ronald W. Barton; Farid Bamdad; Joel Blackman

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Design review report for the SY-101 RAPID mitigation system

International Nuclear Information System (INIS)

SCHLOSSER, R.L.

1999-01-01

This report documents design reviews conducted of the SY-101 Respond And Pump In Days (RAPID) Mitigation System. As part of the SY-101 Surface-Level-Rise Remediation Project, the SY-101 WID Mitigation System will reduce the potential unacceptable consequences of crust growth in Tank 241-SY-101 (SY-101). Projections of the crust growth rate indicate that the waste level in the tank may reach the juncture of the primary and secondary confinement structures of the tank late in 1999. Because of this time constraint, many design activities are being conducted in parallel and design reviews were conducted for system adequacy as well as design implementation throughout the process. Design implementation, as used in this design review report, is the final component selection (e.g., which circuit breaker, valve, or thermocouple) that meets the approved design requirements, system design, and design and procurement specifications. Design implementation includes the necessary analysis, testing, verification, and qualification to demonstrate compliance with the system design and design requirements. Design implementation is outside the scope of this design review. The design activities performed prior to detailed design implementation (i.e., system mission requirements, functional design requirements, technical criteria, system conceptual design, and where design and build contracts were placed, the procurement specification) have been reviewed and are within the scope of this design review report. Detailed design implementation will be controlled, reviewed, and where appropriate, approved in accordance with Tank Waste Remediation System (TWRS) engineering procedures. Review of detailed design implementation will continue until all components necessary to perform the transfer function are installed and tested

Design review report for the SY-101 RAPID mitigation system

Energy Technology Data Exchange (ETDEWEB)

SCHLOSSER, R.L.

1999-05-24

This report documents design reviews conducted of the SY-101 Respond And Pump In Days (RAPID) Mitigation System. As part of the SY-101 Surface-Level-Rise Remediation Project, the SY-101 WID Mitigation System will reduce the potential unacceptable consequences of crust growth in Tank 241-SY-101 (SY-101). Projections of the crust growth rate indicate that the waste level in the tank may reach the juncture of the primary and secondary confinement structures of the tank late in 1999. Because of this time constraint, many design activities are being conducted in parallel and design reviews were conducted for system adequacy as well as design implementation throughout the process. Design implementation, as used in this design review report, is the final component selection (e.g., which circuit breaker, valve, or thermocouple) that meets the approved design requirements, system design, and design and procurement specifications. Design implementation includes the necessary analysis, testing, verification, and qualification to demonstrate compliance with the system design and design requirements. Design implementation is outside the scope of this design review. The design activities performed prior to detailed design implementation (i.e., system mission requirements, functional design requirements, technical criteria, system conceptual design, and where design and build contracts were placed, the procurement specification) have been reviewed and are within the scope of this design review report. Detailed design implementation will be controlled, reviewed, and where appropriate, approved in accordance with Tank Waste Remediation System (TWRS) engineering procedures. Review of detailed design implementation will continue until all components necessary to perform the transfer function are installed and tested.

The necessary guidance on the application of JUSTIFICATION and ALARA by the nuclear authorities, using 'Accountability for Reasonableness' as a decision making process

International Nuclear Information System (INIS)

Veuchelen, Ludo

2008-01-01

Full text: In all branches of law, but foremost in international nuclear law, the global economic system brings along a vast record of Soft Law covering General Principles and Standards. For a part we can find these Soft Law Principles and Standards back in the clothing of hard law, or in the licensing procedures, at the national level. The larger part however is never 'transposed' into national laws and especially the harmonization, the implementation and control of such Principles and Standards remain doubtful. In this paper the focus lies on JUSTIFICATION and ALARA, as the main nuclear safety principles, accepted world-wide. The regulatory guidance and demonstration of these Principles, indicating which (numerical) safety levels or safety objectives are mandatory and which are only guidance should be undertaken by the international regulators and authorities, but are often lacking. It is the aim of this paper to come up with a better procedural framework for a priority setting process by nuclear authorities. Establishing a fair process for priority setting is easier than agreeing on principles. We use the idea of 'Accountability for Reasonableness', developed in the field of Health Care Management. An ideal model of priority setting within the JUSTIFICATION/ALARA approach will need to specify what should be done (i.e. justified ethically) and how it can be done (i.e. based in empirical reality and on benchmarking), to reach optimal levels of nuclear safety. (author)

A Literature Review: Website Design and User Engagement.

Science.gov (United States)

Garett, Renee; Chiu, Jason; Zhang, Ly; Young, Sean D

2016-07-01

Proper design has become a critical element needed to engage website and mobile application users. However, little research has been conducted to define the specific elements used in effective website and mobile application design. We attempt to review and consolidate research on effective design and to define a short list of elements frequently used in research. The design elements mentioned most frequently in the reviewed literature were navigation, graphical representation, organization, content utility, purpose, simplicity, and readability. We discuss how previous studies define and evaluate these seven elements. This review and the resulting short list of design elements may be used to help designers and researchers to operationalize best practices for facilitating and predicting user engagement.

New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Padilla C, I.

1991-01-01

In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program

Computational protein design: a review

International Nuclear Information System (INIS)

Coluzza, Ivan

2017-01-01

Proteins are one of the most versatile modular assembling systems in nature. Experimentally, more than 110 000 protein structures have been identified and more are deposited every day in the Protein Data Bank. Such an enormous structural variety is to a first approximation controlled by the sequence of amino acids along the peptide chain of each protein. Understanding how the structural and functional properties of the target can be encoded in this sequence is the main objective of protein design. Unfortunately, rational protein design remains one of the major challenges across the disciplines of biology, physics and chemistry. The implications of solving this problem are enormous and branch into materials science, drug design, evolution and even cryptography. For instance, in the field of drug design an effective computational method to design protein-based ligands for biological targets such as viruses, bacteria or tumour cells, could give a significant boost to the development of new therapies with reduced side effects. In materials science, self-assembly is a highly desired property and soon artificial proteins could represent a new class of designable self-assembling materials. The scope of this review is to describe the state of the art in computational protein design methods and give the reader an outline of what developments could be expected in the near future. (topical review)

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

1998-01-01

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report.

Safeguards by Design Challenge

Energy Technology Data Exchange (ETDEWEB)

Alwin, Jennifer Louise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-09-13

The International Atomic Energy Agency (IAEA) defines Safeguards as a system of inspection and verification of the peaceful uses of nuclear materials as part of the Nuclear Nonproliferation Treaty. IAEA oversees safeguards worldwide. Safeguards by Design (SBD) involves incorporation of safeguards technologies, techniques, and instrumentation during the design phase of a facility, rather that after the fact. Design challenge goals are the following: Design a system of safeguards technologies, techniques, and instrumentation for inspection and verification of the peaceful uses of nuclear materials. Cost should be minimized to work with the IAEA’s limited budget. Dose to workers should always be as low are reasonably achievable (ALARA). Time is of the essence in operating facilities and flow of material should not be interrupted significantly. Proprietary process information in facilities may need to be protected, thus the amount of information obtained by inspectors should be the minimum required to achieve the measurement goal. Then three different design challenges are detailed: Plutonium Waste Item Measurement System, Marine-based Modular Reactor, and Floating Nuclear Power Plant (FNPP).

Safeguards by Design Challenge

International Nuclear Information System (INIS)

Alwin, Jennifer Louise

2016-01-01

The International Atomic Energy Agency (IAEA) defines Safeguards as a system of inspection and verification of the peaceful uses of nuclear materials as part of the Nuclear Nonproliferation Treaty. IAEA oversees safeguards worldwide. Safeguards by Design (SBD) involves incorporation of safeguards technologies, techniques, and instrumentation during the design phase of a facility, rather that after the fact. Design challenge goals are the following: Design a system of safeguards technologies, techniques, and instrumentation for inspection and verification of the peaceful uses of nuclear materials. Cost should be minimized to work with the IAEA's limited budget. Dose to workers should always be as low are reasonably achievable (ALARA). Time is of the essence in operating facilities and flow of material should not be interrupted significantly. Proprietary process information in facilities may need to be protected, thus the amount of information obtained by inspectors should be the minimum required to achieve the measurement goal. Then three different design challenges are detailed: Plutonium Waste Item Measurement System, Marine-based Modular Reactor, and Floating Nuclear Power Plant (FNPP).

Building arrangement and site layout design guides for on site low level radioactive waste storage facilities

International Nuclear Information System (INIS)

McMullen, J.W.; Feehan, M.J.

1986-01-01

Many papers have been written by AE's and utilities describing their onsite storage facilities, why they are needed, NRC regulations, and disposal site requirements. This paper discusses a typical storage facility and address the design considerations and operational aspects that are generally overlooked when designing and siting a low level radioactive waste storage facility. Some topics to be addressed are: 1. Container flexibility; 2. Modular expansion capabilities; 3. DOT regulations; 4. Meterological requirements; 5. OSHA; 6. Fire protection; 7. Floods; 8. ALARA

Peer review in design: Understanding the impact of collaboration on the review process and student perception

Science.gov (United States)

Mandala, Mahender Arjun

A cornerstone of design and design education is frequent situated feedback. With increasing class sizes, and shrinking financial and human resources, providing rich feedback to students becomes increasingly difficult. In the field of writing, web-based peer review--the process of utilizing equal status learners within a class to provide feedback to each other on their work using networked computing systems--has been shown to be a reliable and valid source of feedback in addition to improving student learning. Designers communicate in myriad ways, using the many languages of design and combining visual and descriptive information. This complex discourse of design intent makes peer reviews by design students ambiguous and often not helpful to the receivers of this feedback. Furthermore, engaging students in the review process itself is often difficult. Teams can complement individual diversity and may assist novice designers collectively resolve complex task. However, teams often incur production losses and may be impacted by individual biases. In the current work, we look at utilizing a collaborative team of reviewers, working collectively and synchronously, in generating web based peer reviews in a sophomore engineering design class. Students participated in a cross-over design, conducting peer reviews as individuals and collaborative teams in parallel sequences. Raters coded the feedback generated on the basis of their appropriateness and accuracy. Self-report surveys and passive observation of teams conducting reviews captured student opinion on the process, its value, and the contrasting experience they had conducting team and individual reviews. We found team reviews generated better quality feedback in comparison to individual reviews. Furthermore, students preferred conducting reviews in teams, finding the process 'fun' and engaging. We observed several learning benefits of using collaboration in reviewing including improved understanding of the assessment

A Literature Review: Website Design and User Engagement.

OpenAIRE

Garett, R; Chiu, J; Zhang, L; Young, SD

2016-01-01

Proper design has become a critical element needed to engage website and mobile application users. However, little research has been conducted to define the specific elements used in effective website and mobile application design. We attempt to review and consolidate research on effective design and to define a short list of elements frequently used in research. The design elements mentioned most frequently in the reviewed literature were navigation, graphical representation, organization, c...

Review of research in feature based design

NARCIS (Netherlands)

Salomons, O.W.; van Houten, Frederikus J.A.M.; Kals, H.J.J.

1993-01-01

Research in feature-based design is reviewed. Feature-based design is regarded as a key factor towards CAD/CAPP integration from a process planning point of view. From a design point of view, feature-based design offers possibilities for supporting the design process better than current CAD systems

Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

International Nuclear Information System (INIS)

Dippre, M. A.

2003-01-01

A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational

Sampling and Characterization of 618-2 Anomalous Material

International Nuclear Information System (INIS)

Zacharias, A.E.

2006-01-01

This as low as reasonably achievable (ALARA) Level II review documents radiological engineering and administrative controls necessary for the sampling and characterization of anomalous materials discovered during the remediation of the 618-2 solid waste burial ground. The goals of these engineering and administrative controls are to keep personnel exposure ALARA, control contamination levels, and minimize potential for airborne contamination. Excavation of the 618-2 Burial Ground has produced many items of anomalous waste. Prior to temporary packaging and/or storage, these items have been characterized in the field to identify radiological and industrial safety conditions. Further sampling and characterization of these items, as well as those remaining from an excavated combination safe, is the subject of this ALARA Level II review. An ALARA in-progress review will also be performed prior to sampling and characterization of 618-2 anomalous materials offering risks of differing natures. General categories of anomalies requiring further characterization include the following: (1) Containers of unknown liquids and/or solids and powders (excluding transuranics); (2) Drums containing unknown liquids and/or solids; (3) Metal containers with unknown contents; and (4) Known or suspected transuranic material.

ALARA - the contribution of the proposed new ionising radiations regulations

International Nuclear Information System (INIS)

Young, T.O.

1982-01-01

This paper describes the proposed regulatory requirements and appropriate guidance contained in the approved code of practice on ionising radiations which are designed to support and help reach the objective of keeping radiation doses as low as reasonably achievable. This is discussed against the background of factory legislation, and the way in which the form of the proposed legislation handles this topic is illustrated. The measures required by the proposed legislation are reviewed, both as direct measures designed to create a climate of dose reduction, and as general measures designed to achieve the same end by means of a wide range of requirements. (author)

Office design and health: a systematic review.

Science.gov (United States)

Richardson, Ann; Potter, John; Paterson, Margaret; Harding, Thomas; Tyler-Merrick, Gaye; Kirk, Ray; Reid, Kate; McChesney, Jane

2017-12-15

To carry out a systematic review of recent research into the effects of workplace design, comparing individual with shared workspaces, on the health of employees. The research question was "Does workplace design (specifically individual offices compared with shared workspaces) affect the health of workers?" A literature search limited to articles published between 2000 and 2017 was undertaken. A systematic review was carried out, and the findings of the reviewed studies grouped into themes according to the primary outcomes measured in the studies. The literature search identified 15 relevant studies addressing health effects of shared or open-plan offices compared with individual offices. Our systematic review found that, compared with individual offices, shared or open-plan office space is not beneficial to employees' health, with consistent findings of deleterious effects on staff health, wellbeing and productivity. Our findings are also consistent with those of earlier reviews. These findings have public health implications for the New Zealand workforce. Decisions about workplace design should include weighing the short-term financial benefits of open-plan or shared workspaces against the significant harms, including increased sickness absence, lower job satisfaction and productivity, and possible threats to recruitment and retention of staff.

Review of standards and guidelines pertinent to DOE's Remedial Action programs

International Nuclear Information System (INIS)

Soldat, J.K.; Denham, D.H.

1985-01-01

A number of radiological standards, guidelines, and dose criteria have been promulgated that may be relevant to the Department of Energy's (DOE) Remedial Action programs. Some of these are being applied to remedial actions undertaken by DOE to ensure that health and safety aspects are adequately addressed. Pacific Northwest Laboratory staff reviewed existing and proposed environmental radiological standards and criteria for their applicability to DOE's Remedial Action Programs. National and international environmental standards and criteria, and studies conducted by other DOE contractors were reviewed. The review indicated that there is a lack of uniformity between the dose guidelines developed by the various agencies. A uniform dose standard is needed for DandD, at least as an upper limit with application of the ALARA philosophy. 33 references, 5 tables

A systematic review of protocol studies on conceptual design cognition: design as search and exploration

OpenAIRE

Hay, Laura; Duffy, Alex H.B.; McTeague, Chris; Pidgeon, Laura M.; Vuletic, Tijana; Grealy, Madeleine

2017-01-01

This paper reports findings from the first systematic review of protocol studies focusing specifically on conceptual design cognition, aiming to answer the following research question: What is our current understanding of the cognitive processes involved in conceptual design tasks carried out by individual designers? We reviewed 47 studies on architectural design, engineering design and product design engineering. This paper reports 24 cognitive processes investigated in a subset of 33 studie...

Design Review Closure Report for the SY-101 Rapid Transfer System

International Nuclear Information System (INIS)

POWELL, W.J.

1999-01-01

The purpose of this report, is to document closure of design review open items, resulting from design reviews conducted for the SY-101 Respond And Pump In Days (RAPID) Transfer System. Results of the various design reviews were documented in the Design Review Report for The SY-101 Rapid Mitigation System, HNF-4519. In that report, twenty-three open items were identified. In this report the 23 items are reviewed and statused

Design Review Closure Report for the SY-101 Rapid Transfer System

Energy Technology Data Exchange (ETDEWEB)

POWELL, W.J.

1999-11-29

The purpose of this report, is to document closure of design review open items, resulting from design reviews conducted for the SY-101 Respond And Pump In Days (RAPID) Transfer System. Results of the various design reviews were documented in the Design Review Report for The SY-101 Rapid Mitigation System, HNF-4519. In that report, twenty-three open items were identified. In this report the 23 items are reviewed and statused.

Design review report for rotary mode core sample truck (RMCST) modifications for flammable gas tanks, preliminary design

International Nuclear Information System (INIS)

Corbett, J.E.

1996-02-01

This report documents the completion of a preliminary design review for the Rotary Mode Core Sample Truck (RMCST) modifications for flammable gas tanks. The RMCST modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to validate basic design assumptions and concepts to support a path forward leading to a final design. The conclusion reached by the review committee was that the design was acceptable and efforts should continue toward a final design review

Application of project design peer review to improve quality assurance

International Nuclear Information System (INIS)

McClure, F.E.

1989-01-01

DOE ORDER 5481.1B Safety Analysis and Review Systems and DOE ORDER 6430.1A General Design Criteria require that the design of facilities shall incorporate the necessary Quality Assurance review requirements to assure that the established program quality assurance objectives are met in the design criteria and the construction documents. The use of Project Design Peer Review to satisfy these requirements is presented. The University of California manages the Lawrence Berkeley Laboratory, the Lawrence Livermore National Laboratory, and the Los Alamos National Scientific Laboratory. The 1988 University Seismic Safety Policy requires the use of independent Project Design Peer Review in its capital improvement and seismic reconstruction program

Application of design review in the heavy power plant industry

International Nuclear Information System (INIS)

Yound, N.

1977-01-01

The application of design review technique in a company engaged in the design and manufacture of turbo-generators for power stations, is described. One benefit arising from design review is its use as a means of design verification. (U.K.)

Human-system interface design review guideline -- Review software and user's guide: Final report. Revision 1, Volume 3

International Nuclear Information System (INIS)

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 3 contains an interactive software application of the NUREG-0700, Revision 1 guidance and a user's guide for this software. The software supports reviewers during review preparation, evaluation design using the human factors engineering guidelines, and in report preparation. The user's guide provides system requirements and installation instructions, detailed explanations of the software's functions and features, and a tutorial on using the software

Preliminary design review report for K Basin Dose Reduction Project

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-01-01

The strategy for reducing radiation dose, originating from radionuclides absorbed in the K East Basin concrete, is to raise the pool water level to provide additional shielding. This report documents a preliminary design review conducted to ensure that design approaches for cleaning/coating basin walls and modifying other basin components were appropriate. The conclusion of this review was that design documents presently conclusion of this review was that design documents presently completed or in process of modification are and acceptable basis for proceeding to complete the design

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

International Nuclear Information System (INIS)

1997-01-01

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

Pacific Northwest Laboratory ALARA report for Calendar Year 1994

International Nuclear Information System (INIS)

Keller, S.L.

1995-08-01

This report provides summary results of the Calendar Year (CY) 1994 As Low As Reasonably Achievable (ALARA) Program performance at the Pacific Northwest Laboratory (PNL). This report includes data regarding performance in the area of personnel exposures to radiation, skin contaminations, control of contaminated areas, minimization of radioactive waste, and control of radioactive releases. In CY 1994: (1) The collective total effective dose equivalent to PNL employees during 1994 was 55 person-rem. The Field Dosimetry Services of the Radiological Control Department, Technical Support Section, projected that no PNL employee's dose would exceed 2 rem based on dosimeters processed during the year; no worker actually exceeded the projection-by the end of CY 1994. The maximum dose to any individual was 1.11 rem. (2) There were 34 instances of skin and personal-clothing contamination events for PNL employees during 1994. Eighteen of these contamination events occurred at the 324 Building; eleven occurred at the 325 Building; two occurred in the 327 Building; one occurred in the 326 Building; one occurred in the 3708 Building; and one occurred in the RTL Building. (3) PNL facilities contained 12 Airborne Radioactivity Areas, and 60 Contamination Areas and High Contamination Areas. The area of the Airborne Radioactivity Areas was 383 m 2 (4125 ft 2 ). The area of the Contamination Areas was 5290 m 2 (56,947 ft 2 ). The area of the High Contamination Areas was 266 m 2 (2863 ft 2 ). (4) PNL disposed of 10.5 m 3 (371 ft 3 ) of compacted low level waste. Also disposed was 423 m 3 (14,949 ft 3 ) of noncompacted low level and mixed waste that was not subject to volume reduction. The total radioactivity of the disposed waste was 1217 Ci. (5) PNL facilities released 165.2 Ci of noble gas, 3.0E-5 Ci of airborne particulate radioactive material, and 12.2 Ci of tritium to the environment

Design review of SPWR with PSA methodology

International Nuclear Information System (INIS)

Oikawa, Tetsukuni; Muramatsu, Ken; Iwamura, Takamichi; Tone, Tatsuzo; Kasahara, Takeo; Mizuno, Yoshio

1993-01-01

This paper presents the procedures and results of a PSA (Probabilistic Safety Assessment) of the SPWR (System-Integrated PWR), which is being developed at the Japan Atomic Energy Research Institute (JAERI) as a medium sized innovative passive safe reactor, to assist in the design improvement of the SPWR by reviewing the design and identifying the design weaknesses. This PSA was performed in four steps: (1) identification of initiating events by the failure mode effect analysis and other methods, (2) delineation of accident sequences for three selected initiating events using accident progression flow charts and event trees, (3) quantification of event trees based on the review of past PSAs for LWRs, and (4) sensitivity analysis and interpretation of results. Qualitative and quantitative results of PSA provided very useful information for decision makings of design improvement and recommendations for further consideration in the process of detailed design

Advanced human-system interface design review guidelines

International Nuclear Information System (INIS)

O'Hara, J.M.

1990-01-01

Advanced, computer-based, human-system interface designs are emerging in nuclear power plant (NPP) control rooms. These developments may have significant implications for plant safety in that they will greatly affect the ways in which operators interact with systems. At present, however, the only guidance available to the US Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces, NUREG-0700, was written prior to these technological changes and is thus not designed to address them. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline for use in performing human factors reviews of advanced operator interfaces. This guideline will be implemented, in part, as a portable, computer-based, interactive document for field use. The paper describes the overall guideline development methodology, the present status of the document, and the plans for further guideline testing and development. 21 refs., 3 figs

Design/Operations review of core sampling trucks and associated equipment

International Nuclear Information System (INIS)

Shrivastava, H.P.

1996-01-01

A systematic review of the design and operations of the core sampling trucks was commissioned by Characterization Equipment Engineering of the Westinghouse Hanford Company in October 1995. The review team reviewed the design documents, specifications, operating procedure, training manuals and safety analysis reports. The review process, findings and corrective actions are summarized in this supporting document

Operability design review of prototype large breeder reactor (PLBR) designs. Final report, September 1981

International Nuclear Information System (INIS)

Beakes, J.H.; Ehman, J.R.; Jones, H.M.; Kinne, B.V.T.; Price, C.M.; Shores, S.P.; Welch, J.K.

1981-09-01

Prototype Large Breeder Reactor (PLBR) designs were reviewed by personnel with extensive power plant operations experience. Fourteen normal and off-normal events, such as startup, shutdown, refueling, reactor scram and loss of feedwater, were evaluated using an operational evaluation methodology which is designed to facilitate talk-through sessions on operational events. Human factors engineers participated in the review and assisted in developing and refining the review methodologies. Operating experience at breeder reactor facilities such as Experimental Breeder Reactor-II (EBR-II), Enrico Fermi Atomic Power Plant - Unit 1, and the Fast Flux Test Facility (FFTF) was gathered, analyzed, and used to determine whether lessons learned from operational experience had been incorporated into the PLBR designs. This eighteen month effort resulted in approximately one hundred specific recommendations for improving the operability of PLBR designs

Savannah River Site dose control

International Nuclear Information System (INIS)

Smith, L.S.

1992-01-01

Health physicists from the Brookhaven National Laboratory (BNL) visited the Savannah River Site (SRS) as one of 12 facilities operated by the Department of Energy (DOE) contractors with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). Their charter was to review, evaluate and summarize as low as reasonably achievable (ALARA) techniques, methods and practices as implemented. This presentation gives an overview of the two selected ALARA practices implemented at the SRS: Administrative Exposure Limits and Goal Setting. These dose control methods are used to assure that individual and collective occupational doses are ALARA and within regulatory limits

Psychogeriatric inpatient unit design: a literature review.

Science.gov (United States)

Dobrohotoff, John T; Llewellyn-Jones, Robert H

2011-03-01

In many parts of the world the provision of psychogeriatric inpatient units (PGUs) remains limited. More units will be required over coming decades given rapid population aging. Medline (1950-2010), psycINFO (1806-2009), EMBASE (1980-2009) and CINAHL (1982-2009) were searched for papers about PGU design. Selected non-peer reviewed literature such as government reports and unpublished academic dissertations were also reviewed. Data were also obtained from the literature related to general adult psychiatry inpatient units where there was limited information from studies of units designed for older people. Over 200 papers were reviewed and 130 were included. There are few good quality studies to guide the design of acute PGUs and much of the existing literature is based on opinion and anecdote or, at best, based on observational studies. Randomized controlled studies comparing different designs and assessing outcomes are virtually non-existent. Several studies have identified violence and trauma resulting from hospitalization as significant problems with current acute PGU care. Despite its limitations the available literature provides useful guidance on how PGU design can optimize patient and staff safety and improve clinical outcomes. There are significant problems with current acute PGUs, and patient mix on existing units is an important issue. Future research should examine patient and staff perceptions of different PGU ward environments, the relationship between ward design and clinical outcomes, the effects of segregating patients with challenging behaviors in dementia and the benefits or otherwise of gender segregation.

Study-design selection criteria in systematic reviews of effectiveness of health systems interventions and reforms: A meta-review.

Science.gov (United States)

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

2012-03-01

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

Design reviews: A process perspective for improved efficiency and effectiveness

CSIR Research Space (South Africa)

Young, M

2013-06-01

Full Text Available -Black and Iverson 1994) and systematic (Pahl and Beitz 1996) review of the design. Even though it is advisable to use a generic checklist or compliance matrix as the basis for determining these criteria, it is important to use these generics as a guideline only... review to allow sufficient time to address any outstanding issues prior to review meeting. Evolutionary design reviews. When dealing with complex systems, it is advisable to conduct sub-system reviews, building up to a system review that deals...

Maintaining radiation exposures as low as reasonably achievable (ALARA) for dental personnel operating portable hand-held x-ray equipment.

Science.gov (United States)

McGiff, Thomas J; Danforth, Robert A; Herschaft, Edward E

2012-08-01

Clinical experience indicates that newly available portable hand-held x-ray units provide advantages compared to traditional fixed properly installed and operated x-ray units in dental radiography. However, concern that hand-held x-ray units produce higher operator doses than fixed x-ray units has caused regulatory agencies to mandate requirements for use of hand-held units that go beyond those recommended by the manufacturer and can discourage the use of this technology. To assess the need for additional requirements, a hand-held x-ray unit and a pair of manikins were used to measure the dose to a simulated operator under two conditions: exposures made according to the manufacturer's recommendations and exposures made according to manufacturer's recommendation except for the removal of the x-ray unit's protective backscatter shield. Dose to the simulated operator was determined using an array of personal dosimeters and a pair of pressurized ion chambers. The results indicate that the dose to an operator of this equipment will be less than 0.6 mSv y⁻¹ if the device is used according to the manufacturer's recommendations. This suggests that doses to properly trained operators of well-designed, hand-held dental x-ray units will be below 1.0 mSv y⁻¹ (2% of the annual occupational dose limit) even if additional no additional operational requirements are established by regulatory agencies. This level of annual dose is similar to those reported as typical dental personnel using fixed x-ray units and appears to satisfy the ALARA principal for this class of occupational exposures.

Cold vacuum drying facility 90% design review

International Nuclear Information System (INIS)

O'Neill, C.T.

1997-01-01

This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage

Cold vacuum drying facility 90% design review

Energy Technology Data Exchange (ETDEWEB)

O`Neill, C.T.

1997-05-02

This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage.

Design review of the INTOR mechanical configuration

International Nuclear Information System (INIS)

Brown, T.G.

1981-01-01

The INTOR conceptual design has been carried out by design teams working in the home countries with periodic workshop sessions in Vienna to review the ongoing work and to make decisions on the evolving design. The decisions taken at each workshop session were then incorporated into each national design activity, so that the four national design contributions would progressively converge toward a single design with increasingly greater detail. This paper defines the final INTOR configuration that has evolved during the conceptual design phase, defining the major system design alternatives that were considered and the rationale for selecting the final system configuration

Review of design optimization methods for turbomachinery aerodynamics

Science.gov (United States)

Li, Zhihui; Zheng, Xinqian

2017-08-01

In today's competitive environment, new turbomachinery designs need to be not only more efficient, quieter, and ;greener; but also need to be developed at on much shorter time scales and at lower costs. A number of advanced optimization strategies have been developed to achieve these requirements. This paper reviews recent progress in turbomachinery design optimization to solve real-world aerodynamic problems, especially for compressors and turbines. This review covers the following topics that are important for optimizing turbomachinery designs. (1) optimization methods, (2) stochastic optimization combined with blade parameterization methods and the design of experiment methods, (3) gradient-based optimization methods for compressors and turbines and (4) data mining techniques for Pareto Fronts. We also present our own insights regarding the current research trends and the future optimization of turbomachinery designs.

Proceedings of the 6. conference days on radioprotection optimization in the nuclear, industrial and medical domains

International Nuclear Information System (INIS)

Vial, Eric; Bernier, Marie-Odile; De Vita, Antoine; Pignot, Christine; Bardelay, Chantal; Godet, Jean-Luc; Perrin, Marie-Line; Saad, Nawal; Deboodt, Pascal P.A.; Faure, Sophie; Fusil, Laurence; Alvarez, Manuel; Tourneux, C.; Barbey, Pierre; Pigree, Gilbert; Lemarchand, Maxime; Buchaniec, Remi; Rocourt, Nathalie; Bouden, Helene; Lasselin, Stephanie; Moeneclaey, Ludivine; Rebullida, Delphine; Werquin, Marie Odile; Dubus, Francois; Ponsard, Samuel; Marques, Sophie; K-Zerho, R.; Vacher, F.; Vrammout, D.; Guillot, E.; Fucks, I.; Moukarzel, Marianne; Ryckx, Nick; Verdun, Francis R.; Lefaure, Christian; Balduyck, Sebastien; Cruz Suarez, Rodolfo; ); Bouvy, Christophe; Geets, Jean-Michel; Nactergal, Benoit; Davet, Laurent; Carlier, Pierre; Lereculey, Clement; Livolsi, Paul; PIN, Alain; Ducou le Pointe, Hubert; Le Faou, Yann; Courageot, Estelle; Gaillard-Lecanu, Emmanuelle; Kutschera, Reinald; Le Meur, Gaelle; Lantheaume, Noel; Schiedts, Dominique; Nouveau, Philippe; Walterscheid, Bertrand; Humbert, Edouard; Tranchant, Philippe; Dabat-Blondeau, Charlotte; Renard, Francois; Lucas, Jean-Yves; Fritioff, Karin; Svedberg, Torgny; Carlson, Marie; Hennigor, Staffan; Schieber, Caroline; Andresz, Sylvain; Roch, Patrice; Celier, David; Aubert, Bernard; Etard, Cecile; Bouette, Aurelien; Carette, M.F.; Haddad, S.; Khalil, A.; Foulquier, J.N.; Parrot, A.; Ceyrolle, C.; Bechard, Pascal; Clero, E.; Leuraud, K.; Laurier, D.; Couzinet, M.; LE GUEN, B.; Davesne, Estelle; Blanchardon, Eric; Franck, Didier; Quesne, Benoit; De Vita, Antoine; Chojnacki, Eric; Grandeau, E.; Dumont, N.; Cattelotte, J.; Dine, Pierre Emmanuel; Guersen, Joel; Nwatsock, Joseph Francis; Boyer, Louis; Karmouche, K.; Moyon, J.B.; Cassagnes, L.; Garcier, J.M.; Lortal, B.; Caron, J.; Karst, M.; Rage, Estelle; Caer-Lorho, Sylvaine; Drubay, Damien; Ancelet, Sophie; Laurier, Dominique; Laroche, Pierre; Sans, Philippe; Tournier, Helene; Zvorykin, Sonia

2014-06-01

This 6. ALARA conference was jointly organised by the French Society of Radiation Protection (SFRP) and several professional associations (ABR, AFPPE, ARRAD, ATSR, RAMIP, SFPM, SFR). The conference was the occasion to review all aspects relative to the issues of radioprotection optimization and to its implementation to workers, patients and the public in the nuclear, industrial and medical domains. A particular attention must be given to the application of the ALARA principle in all sectors relevant to radioprotection, especially in a context characterized by: big dismantling works under preparation in the French nuclear park, an increased use of X-radiation in the medical domain - involving both patients and medical personnel, new knowledge concerning the health effects of ionizing radiations, and an evolution of European and international radioprotection safety standards. All these aspects were discussed during these conference days. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Review of the evolution of workers/patients exposure in France and comparison with international data (E. Vial); 2 - Status of low dose epidemiology (M.O. Bernier); 3 - Radioprotection optimization method at the MELOX plant (A. De Vita); 4 - Elaboration method for the annual dosimetric objective of the French nuclear park (C. Pignot); 5 - Optimisation principle in the new EURATOM Directive (N. Saad); 6 - Integrated management of radiological and non-radiological risks: the inevitable challenge (P. Deboodt); 7 - Radiological and conventional risks: the French Atomic Energy Commission (CEA) integrated approach (S. Faure); 8 - EVEREST (Evolving towards an entry into controlled areas in street clothes, M. Alvarez); 9 - Example of multi-risk management in the medical domain (C. Tourneux); 10 - Radioprotection optimisation in the research domain (P. Barbey); 11 - Child scanning dosimetry

Flexible receiver adapter formal design review

International Nuclear Information System (INIS)

Krieg, S.A.

1995-01-01

This memo summarizes the results of the Formal (90%) Design Review process and meetings held to evaluate the design of the Flexible Receiver Adapters, support platforms, and associated equipment. The equipment is part of the Flexible Receiver System used to remove, transport, and store long length contaminated equipment and components from both the double and single-shell underground storage tanks at the 200 area tank farms

Design review of the N Reactor

International Nuclear Information System (INIS)

1986-09-01

This review of the design features of the N Reactor was initiated at the request of the Secretary of Energy, John S. Herrington, shortly after, and as a consequence of, reports of the accident at the Soviet reactor complex located at Chernobyl, on April 26, 1986. In the review, special attention was given to those plant systems which are most important in preventing the release of radioactive materials from the plant in the event of combined major equipment failures and human errors. Also, the review studied the potential effects of various severe accident sequences, and addressed the question of whether an event similar in causes or consequences to the Chernobyl accident could occur in the N Reactor. In light of experiences at both Three Mile Island and Chernobyl, the potential for accumulation of hydrogen in excess of flammable limits was given particular attention. The review team was also asked to identify possible improvements to the N Reactor plant, and to evaluate the effects and significance of service-induced degradation. The overall conclusion of the design review is that the N Reactor is safe to operate and that there is no reason to stop or alter its operation in any major respect at this time. Certain additional analyses and testing, are recommended to provide a firmer basis for decisions on long-term operation and on measures which may be needed in the future to accommodate long-term operation

Spent Nuclear Fuel Cold Vacuum Drying facility comprehensive formal design review report

International Nuclear Information System (INIS)

HALLER, C.S.

1999-01-01

The majority of the Cold Vacuum Drying Facility (CVDF) design and construction is complete; isolated portions are still in the design and fabrication process. The project commissioned a formal design review to verify the sufficiency and accuracy of current design media to assure that: (1) the design completely and accurately reflects design criteria, (2) design documents are consistent with one another, and (3) the design media accurately reflects the current design. This review is a key element in the design validation and verification activities required by SNF-4396, ''Design Verification and Validation Plan For The Cold Vacuum Drying Facility''. This report documents the results of the formal design review

Review of Designs for Haptic Data Visualization.

Science.gov (United States)

Paneels, Sabrina; Roberts, Jonathan C

2010-01-01

There are many different uses for haptics, such as training medical practitioners, teleoperation, or navigation of virtual environments. This review focuses on haptic methods that display data. The hypothesis is that haptic devices can be used to present information, and consequently, the user gains quantitative, qualitative, or holistic knowledge about the presented data. Not only is this useful for users who are blind or partially sighted (who can feel line graphs, for instance), but also the haptic modality can be used alongside other modalities, to increase the amount of variables being presented, or to duplicate some variables to reinforce the presentation. Over the last 20 years, a significant amount of research has been done in haptic data presentation; e.g., researchers have developed force feedback line graphs, bar charts, and other forms of haptic representations. However, previous research is published in different conferences and journals, with different application emphases. This paper gathers and collates these various designs to provide a comprehensive review of designs for haptic data visualization. The designs are classified by their representation: Charts, Maps, Signs, Networks, Diagrams, Images, and Tables. This review provides a comprehensive reference for researchers and learners, and highlights areas for further research.

On-line Peer Review in Teaching Design-oriented Courses

Directory of Open Access Journals (Sweden)

Hai Ning

2004-02-01

Full Text Available Peer review has been one of the very important designfacilitating processes practiced in education field, particularly in design-oriented courses such as MIT's 2.007 Robot Design. Typically students exchange ideas sketched on a piece of paper and critique on each other's design within a small team. We designed PREP web application backed up by a range of web services that handle the peer-review process on-line, and we argue that this is a significant step towards supporting designoriented course on-line. We believe that the lessons learned could be applied to other interested institutes that offer designoriented courses.

Role of membrane technology to achieve ALARA concept in reprocessing plant: utilization of low pressure reverse osmosis for treatment of delay tank solutions

International Nuclear Information System (INIS)

Pabby, Anil K.; Sonawane, J.V.; Rathore, N.S.; Gupta, S.K.; Roy, S.C.; Venugopalan, A.K.; Chagrani, R.D.; Dey, P.K.; Prabhakar, S.; Tiwari, P.K.

2004-01-01

Reverse osmosis is a well-developed technology. The systems have been used in industrial settings for many years with applications to separation, concentration of product streams and waste water treatment. The technology has been used for removal of the radionuclides from low-level liquid wastes, such as waste streams at nuclear power plants. Because reverse osmosis rejects nearly all contaminants from a solution the high purity product water may be recycled within the power plant, or is usually of such low activity that it is suitable for discharge to the environment. This technology will help in achieving ALARA concept which will be beneficial for the environment. In the present study, the removal of alpha and beta activities from delay tank solution is planned

Design Review Report for Concrete Cover Block Replaced by Steel Plate

Energy Technology Data Exchange (ETDEWEB)

JAKA, O.M.

2000-07-27

The design for the steel cover plates to replace concrete cover blocks for U-109 was reviewed and approved in a design review meeting. The design for steel plates to replace concrete blocks were reviewed and approved by comparison and similarity with U-109 for the following additional pits: 241-U-105. 241-I-103, 241-Ax-101. 241-A-101, 241-SX-105, 241-S-A, 241-S-C, 241-SX-A.

Design iteration in construction projects – Review and directions

Directory of Open Access Journals (Sweden)

Purva Mujumdar

2018-03-01

Full Text Available Design phase of any construction project involves several designers who exchange information with each other most often in an unstructured manner throughout the design phase. When these information exchanges happen to occur in cycles/loops, it is termed as design iteration. Iteration is an inherent and unavoidable aspect of any design phase which requires proper planning. Till date, very few researchers have explored the design iteration (“complexity” in construction sector. Hence, the objective of this paper was to document and review the complexities of iteration during design phase of construction projects for efficient design planning. To achieve this objective, exhaustive literature review on design iteration was done for four sectors – construction, manufacturing, aerospace, and software development. In addition, semi-structured interviews and discussions were done with a few design experts to verify the different dimensions of iteration. Finally, a design iteration framework was presented in this study that facilitates successful planning. Keywords: Design iteration, Types of iteration, Causes and impact of iteration, Models of iteration, Execution strategies of iteration

Independent design review report for truck number 1 modifications for flammable gas tanks

International Nuclear Information System (INIS)

Wilson, G.W.

1997-01-01

The East and West Tank Farm Standing Order 97-01 requires that the PMST be modified to include purging of the enclosed space underneath the shielded receiver weather cover per National Fire Protection Association (NFPA) 496, Purged and Pressurized Enclosures for Electrical Equipment. The Standing Order also requires that the PMST be modified by replacing the existing electrical remote latch (RLU) unit with a mechanical remote latch unit. As the mechanical remote latch unit was exactly like the RLU installed on the Rotary Mode Core Sampler Trucks (RMCST) and the design for the RMCST went through formal design review, replacing the RLU was done utilizing informal design verification and was completed per work package ES-97-0028. As the weather cover purge was similar to the design for the RMCSTS, this design was reviewed using the independent review method with multiple independent reviewers. A function design criteria (WHC-SD-WM-FDC-048, Functional Design Criteria for Core Sampling in Flammable Gas Watch List Tanks) provided the criteria for the modifications. The review consisted of distributing the design review package to the reviewers and collecting and dispositioning the RCR comments. The review package included the ECNs for review, the Design Compliance Matrix, copies of all drawings affected, and copies of outstanding ECNs against these drawings. A final meeting was held to ensure that all reviewers were aware of the changes to ECNs from incorporation of RCR comments

Thermal Analysis of Iodine Satellite (iSAT) from Preliminary Design Review (PDR) to Critical Design Review (CDR)

Science.gov (United States)

Mauro, Stephanie

2016-01-01

The Iodine Satellite (iSAT) is a 12U cubesat with a primary mission to demonstrate the iodine fueled Hall Effect Thruster (HET) propulsion system. The spacecraft (SC) will operate throughout a one year mission in an effort to mature the propulsion system for use in future applications. The benefit of the HET is that it uses a propellant, iodine, which is easy to store and provides a high thrust-to-mass ratio. This paper will describe the thermal analysis and design of the SC between Preliminary Design Review (PDR) and Critical Design Review (CDR). The design of the satellite has undergone many changes due to a variety of challenges, both before PDR and during the time period discussed in this paper. Thermal challenges associated with the system include a high power density, small amounts of available radiative surface area, localized temperature requirements of the propulsion components, and unknown orbital parameters. The thermal control system is implemented to maintain component temperatures within their respective operational limits throughout the mission, while also maintaining propulsion components at the high temperatures needed to allow gaseous iodine propellant to flow. The design includes heaters, insulation, radiators, coatings, and thermal straps. Currently, the maximum temperatures for several components are near to their maximum operation limit, and the battery is close to its minimum operation limit. Mitigation strategies and planned work to solve these challenges will be discussed.

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

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

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

Design for six sigma: A review

Directory of Open Access Journals (Sweden)

Kouroush Jenab

2018-01-01

Full Text Available Six Sigma is recognized as an essential tool for continuous improvement of quality. A large num-ber of publications by various authors reflect the interest in this technique. Reviews of literature on Six Sigma have been done in the past by a few authors. However, considering the contributions in the recent times, a more comprehensive review is attempted here. The authors have examined vari-ous papers and have proposed a different scheme of classification. In addition, certain gaps that would provide hints for further research in Six Sigma have been identified. As a results the rela-tionship between Six Sigma, Design for Six Sigma (DFSS, and how these two concepts support the quality system for organizational learning and innovation performance have been discussed that would help researchers, academicians and practitioners to take a closer look at the growth, devel-opment and applicability of Six Sigma in Design.

Communicating Qualitative Research Study Designs to Research Ethics Review Boards

Science.gov (United States)

Ells, Carolyn

2011-01-01

Researchers using qualitative methodologies appear to be particularly prone to having their study designs called into question by research ethics or funding agency review committees. In this paper, the author considers the issue of communicating qualitative research study designs in the context of institutional research ethics review and offers…

Review on design and control aspects of ankle rehabilitation robots.

Science.gov (United States)

Jamwal, Prashant K; Hussain, Shahid; Xie, Sheng Q

2015-03-01

Ankle rehabilitation robots can play an important role in improving outcomes of the rehabilitation treatment by assisting therapists and patients in number of ways. Consequently, few robot designs have been proposed by researchers which fall under either of the two categories, namely, wearable robots or platform-based robots. This paper presents a review of both kinds of ankle robots along with a brief analysis of their design, actuation and control approaches. While reviewing these designs it was observed that most of them are undesirably inspired by industrial robot designs. Taking note of the design concerns of current ankle robots, few improvements in the ankle robot designs have also been suggested. Conventional position control or force control approaches, being used in the existing ankle robots, have been reviewed. Apparently, opportunities of improvement also exist in the actuation as well as control of ankle robots. Subsequently, a discussion on most recent research in the development of novel actuators and advanced controllers based on appropriate physical and cognitive human-robot interaction has also been included in this review. Implications for Rehabilitation Ankle joint functions are restricted/impaired as a consequence of stroke or injury during sports or otherwise. Robots can help in reinstating functions faster and can also work as tool for recording rehabilitation data useful for further analysis. Evolution of ankle robots with respect to their design and control aspects has been discussed in the present paper and a novel design with futuristic control approach has been proposed.

Design improvements to achieve ALARA exposures to plant personnel at Narora Atomic Power Station (NAPS)

International Nuclear Information System (INIS)

Mittal, S.; Mehta, H.C.; Roy, S.K.

2000-01-01

NAPS is the indigenously designed, constructed and commissioned, first PHWR station of standardized design for 220 MWe station of NPCIL. At NAPS, radiation fields started building up after first start up due to Cobalt-60 and this was a major concern, from collective dose point of view, for carrying out any activity specially around and with in the moderator system. Apart from this system, PHT and fueling machine areas are also vulnerable areas from radiation point of view. To reduce and control the high collective dose consumption, various design modifications; like moderator purification system modifications, changes in heavy water recovery arrangements and FT system, have been carried out at NAPS and these are discussed in this paper. (author)

Design review report for ecn 638521 (241-SX-106 cover plate installation)

Energy Technology Data Exchange (ETDEWEB)

MCVEY, C.B.

1998-10-01

The design for the cover plates on 241-SX-106 was reviewed on 9/10/98. All comments were resolved to the satisfaction of the reviewers. A design calculation for seismic movement was performed and resulted the a design addition to prevent cover block movement. Also calculations were performed for radiological design and are included. The formal design review has no outstanding action items remaining and supports the use of 2 inch steel cover plates to provide personnel shielding and spray knock down protection (as required by the BIO).

Decommissioning Lines-of-Inquiry for Design Review of New Nuclear Facilities

International Nuclear Information System (INIS)

Negin, C.A.; Urland, C.S.

2008-01-01

An independent review of the design of the Salt Waste Processing Facility (SWPF) at Savannah River included a requirement to address the ability to decommission the facility. This paper addresses the lines of inquiry (that were developed for the review and their use in future for reviews of other projects, referred to herein as 'DDLOI'. Decommissioning activities for almost any type of facility are well within the technological state-of-the-art. The major impacts for complications resulting from insufficient consideration during design of a new facility that involves radioactive processes and/or material is the cost of: a) gaining access to high radiation areas and b) dealing with high levels of contamination. For this reason, the DDLOI were developed as a way of raising the awareness of designers and design reviewers to design features that can impede or facilitate ultimate decommissioning. The intent is that this report can be used not only for review, but also by engineers in the early stages of design development when requirements are being assembled. The focus for the DDLOI is on types of facilities that contain nuclear and/or radioactive processes and materials. The level of detail is more specific than would be found in decommissioning plans prepared for regulatory purposes. In commencing this review, the author's could find no precedent for a systematic review of design for decommissioning that included results of a review. Therefore, it was decided to create a report that would provide detailed lines of inquiry along with the rationale for each. The resulting DDLOI report included 21 topical areas for design review. The DDLOI combined the authors' experience in developing baselines for facilities to be deactivated or demolished with prior publications by the U.S. Army and the International Atomic Energy Agency. These two references were found via an Internet search and were the only ones judged to be useful at a field application level. Most others

Mixture design: A review of recent applications in the food industry

OpenAIRE

Yeliz Buruk Şahin; Ezgi Aktar Demirtaş; Nimetullah Burnak

2016-01-01

Design of experiments (DOE) is a systematic approach to applying statistical methods to the experimental process. The main purpose of this study is to provide useful insights into mixture design as a special type of DOE and to present a review of current mixture design applications in the food industry. The theoretical principles of mixture design and its application in the food industry, based on an extensive review of the literature, are described. Mixture design types, such as simplex-latt...

Supporting design reviews with pre-meeting virtual reality environments

NARCIS (Netherlands)

van den Berg, Marc Casper; Hartmann, Timo; de Graaf, Robin S.

2017-01-01

The purpose of this paper is to explore how design reviews can be supported with pre-meeting virtual reality environments. Previous research has not systematically investigated how virtual environments can be used to communicate the design intent (to clients) and to communicate feedback (to design

Development of human factors design review guidelines

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1997-10-01

The Objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, Human factors engineering program review model' and '26, Review criteria for human actors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides be ing performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we well update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

1997-10-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 12 refs., 5 figs., 2 tabs.

Advanced human-system interface design review guidelines

International Nuclear Information System (INIS)

O'Hara, J.M.

1990-01-01

Advanced, computer-based, human-system interface designs are emerging in nuclear power plant control rooms as a result of several factors. These include: (1) incorporation of new systems such as safety parameter display systems, (2) backfitting of current control rooms with new technologies when existing hardware is no longer supported by equipment vendors, and (3) development of advanced control room concepts. Control rooms of the future will be developed almost exclusively with advanced instrumentation and controls based upon digital technology. In addition, the control room operator will be interfacing with more intelligent systems which will be capable of providing information processing support to the operator. These developments may have significant implications for plant safety in that they will greatly affect the operator's role in the system as well as the ways in which he interacts with it. At present, however, the only guidance available to the Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces is NUREG-0700. It is a document which was written prior to these technological changes and is, therefore, tailored to the technologies used in traditional control rooms. Thus, the present guidance needs to be updated since it is inadequate to serve as the basis for NRC staff review of such advanced or hybrid control room designs. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline suitable for use in performing human factors reviews of advanced operator interfaces. This guideline will take the form of a portable, interactive, computer-based document that may be conveniently used by an inspector in the field, as well as a text-based document

Design review plan for Multi-Function Waste Tank Facility (Project W-236A)

International Nuclear Information System (INIS)

Renfro, G.G.

1994-01-01

This plan describes how the Multi-Function Waste Tank Facility (MWTF) Project conducts reviews of design media; describes actions required by Project participants; and provides the methodology to ensure that the design is complete, meets the technical baseline of the Project, is operable and maintainable, and is constructable. Project W-236A is an integrated project wherein the relationship between the operating contractor and architect-engineer is somewhat different than that of a conventional project. Working together, Westinghouse Hanford Company (WHC) and ICF Karser Hanford (ICF KH) have developed a relationship whereby ICF KH performs extensive design reviews and design verification. WHC actively participates in over-the-shoulder reviews during design development, performs a final review of the completed design, and conducts a formal design review of the Safety Class I, ASME boiler and Pressure Vessel Code items in accordance with WHC-CM-6-1, Standard Engineering Practices

Case-only designs in pharmacoepidemiology: a systematic review.

Directory of Open Access Journals (Sweden)

Sandra Nordmann

Full Text Available BACKGROUND: Case-only designs have been used since late 1980's. In these, as opposed to case-control or cohort studies for instance, only cases are required and are self-controlled, eliminating selection biases and confounding related to control subjects, and time-invariant characteristics. The objectives of this systematic review were to analyze how the two main case-only designs - case-crossover (CC and self-controlled case series (SCCS - have been applied and reported in pharmacoepidemiology literature, in terms of applicability assumptions and specificities of these designs. METHODOLOGY/PRINCIPAL FINDINGS: We systematically selected all reports in this field involving case-only designs from MEDLINE and EMBASE up to September 15, 2010. Data were extracted using a standardized form. The analysis included 93 reports 50 (54% of CC and 45 (48% SCCS, 2 reports combined both designs. In 12 (24% CC and 18 (40% SCCS articles, all applicable validity assumptions of the designs were fulfilled, respectively. Fifty (54% articles (15 CC (30% and 35 (78% SCCS adequately addressed the specificities of the case-only analyses in the way they reported results. CONCLUSIONS/SIGNIFICANCE: Our systematic review underlines that implementation of CC and SCCS designs needs to be more rigorous with regard to validity assumptions, as well as improvement in results reporting.

Review of design technology of control rod position indicators

International Nuclear Information System (INIS)

Yu, Je Yong; Huh, Hyung; Kim, Ji Ho; Kim, Jong In; Chang, Moon Hee

1999-10-01

An integral reactor SMART is under development at KAERI. The design characteristics of SMART are radically different from those employer in currently operating loop type water reactors in Korea. The objective of this report is to review the design technology of position indicator, and to study the various sensors which can be used in rod position indicator. Design criteria that rod position indicator should satisfy are also examined. Following position indicators are reviewed in this report. 1. Digital positioning indicator (DRPI), 2. Reed switch type position indicator (RSPT), 3. Choke sensor type position indicator, 4. Ultrasonic sensor type position indicator, 5. Comparison of each position indicator. (author)

Review of Automated Design and Optimization of MEMS

DEFF Research Database (Denmark)

Achiche, Sofiane; Fan, Zhun; Bolognini, Francesca

2007-01-01

carried out. This paper presents a review of these techniques. The design task of MEMS is usually divided into four main stages: System Level, Device Level, Physical Level and the Process Level. The state of the art o automated MEMS design in each of these levels is investigated....

Reconnection of SN-216 to U-D Valve Pit Design Review

International Nuclear Information System (INIS)

REED, R.W.

1999-01-01

The design for the reconnection of SN-216 to U-D valve pit was reviewed on May 24, 1999. All Review Comment Record comments were resolved and closed at this meeting. The review concluded that the reconnection of SN-216 to U-D valve pit was acceptable. The design was approved with the incorporated comments as recorded on the RCR's. No outstanding comments remain

Design considerations for an intelligent mobile robot for mixed-waste inspection

Energy Technology Data Exchange (ETDEWEB)

Sias, F.R.; Dawson, D.M.; Schalkoff, R.J. [Clemson Univ., SC (United States). Dept. of Electrical and Computer Engineering; Byrd, J.S.; Pettus, R.O. [South Carolina Univ., Columbia, SC (United States). Dept. of Electrical and Computer Engineering

1993-06-01

Large quantities of low-level radioactive waste are stored in steel drums at various Department of Energy (DOE) sites in the United States. Much of the stored waste qualifies as mixed waste and falls under Environmental Protection Agency (EPA) regulations that require periodic inspection. A semi-autonomous mobile robot is being developed during Phase 1 of a DOE contract to perform the inspection task and consequently reduce the radiation exposure of inspection personnel to ALARA (as low as reasonably achievable). The nature of the inspection process, the resulting robot design requirements, and the current status of the project are the subjects of this paper.

Design considerations for an intelligent mobile robot for mixed-waste inspection

International Nuclear Information System (INIS)

Sias, F.R.; Dawson, D.M.; Schalkoff, R.J.; Byrd, J.S.; Pettus, R.O.

1993-01-01

Large quantities of low-level radioactive waste are stored in steel drums at various Department of Energy (DOE) sites in the United States. Much of the stored waste qualifies as mixed waste and falls under Environmental Protection Agency (EPA) regulations that require periodic inspection. A semi-autonomous mobile robot is being developed during Phase 1 of a DOE contract to perform the inspection task and consequently reduce the radiation exposure of inspection personnel to ALARA (as low as reasonably achievable). The nature of the inspection process, the resulting robot design requirements, and the current status of the project are the subjects of this paper

Design compliance matrix waste sample container filling system for nested, fixed-depth sampling system

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

This design compliance matrix document provides specific design related functional characteristics, constraints, and requirements for the container filling system that is part of the nested, fixed-depth sampling system. This document addresses performance, external interfaces, ALARA, Authorization Basis, environmental and design code requirements for the container filling system. The container filling system will interface with the waste stream from the fluidic pumping channels of the nested, fixed-depth sampling system and will fill containers with waste that meet the Resource Conservation and Recovery Act (RCRA) criteria for waste that contains volatile and semi-volatile organic materials. The specifications for the nested, fixed-depth sampling system are described in a Level 2 Specification document (HNF-3483, Rev. 1). The basis for this design compliance matrix document is the Tank Waste Remediation System (TWRS) desk instructions for design Compliance matrix documents (PI-CP-008-00, Rev. 0)

A review of design and modeling of magnetorheological valve

Science.gov (United States)

Abd Fatah, Abdul Yasser; Mazlan, Saiful Amri; Koga, Tsuyoshi; Zamzuri, Hairi; Zeinali, Mohammadjavad; Imaduddin, Fitrian

2015-01-01

Following recent rapid development of researches in utilizing Magnetorheological (MR) fluid, a smart material that can be magnetically controlled to change its apparent viscosity instantaneously, a lot of applications have been established to exploit the benefits and advantages of using the MR fluid. One of the most important applications for MR fluid in devices is the MR valve, where it uses the popular flow or valve mode among the available working modes for MR fluid. As such, MR valve is widely applied in a lot of hydraulic actuation and vibration reduction devices, among them are dampers, actuators and shock absorbers. This paper presents a review on MR valve, discusses on several design configurations and the mathematical modeling for the MR valve. Therefore, this review paper classifies the MR valve based on the coil configuration and geometrical arrangement of the valve, and focusing on four different mathematical models for MR valve: Bingham plastic, Herschel-Bulkley, bi-viscous and Herschel-Bulkley with pre-yield viscosity (HBPV) models for calculating yield stress and pressure drop in the MR valve. Design challenges and opportunities for application of MR fluid and MR valve are also highlighted in this review. Hopefully, this review paper can provide basic knowledge on design and modeling of MR valve, complementing other reviews on MR fluid, its applications and technologies.

Final design review report for K basin dose reduction project

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-01-01

The strategy for reducing radiation dose originating from radionuclides absorbed in the K East Basin concrete is to raise the pool water level to provide additional shielding. This report documents a final design review for cleaning/coating basin walls and modifying other basin components where appropriate. The conclusion of this review was that the documents developed constitute an acceptable design for the Dose Reduction Project

Review of methods for the integration of reliability and design engineering

International Nuclear Information System (INIS)

Reilly, J.T.

1978-03-01

A review of methods for the integration of reliability and design engineering was carried out to establish a reliability program philosophy, an initial set of methods, and procedures to be used by both the designer and reliability analyst. The report outlines a set of procedures which implements a philosophy that requires increased involvement by the designer in reliability analysis. Discussions of each method reviewed include examples of its application

Applicability of HRA to support advanced MMI design review

International Nuclear Information System (INIS)

Kim, Inn Seock

2000-01-01

More than half of all incidents in large complex technological systems, particularly in nuclear power or aviation industries, were attributable in some way to human erroneous actions. These incidents were largely due to the human engineering deficiencies of man-machine interface (MMI). In nuclear industry, advanced computer-based MMI designs are emerging as part of new reactor designs. The impact of advanced MMI technology on the operator performance, and as a result, on plant safety should be thoroughly evaluated before such technology is actually adopted in nuclear power plants. This paper discusses the applicability of human reliability analysis (HRA) to support the design review process. Both the first-generation and the second-generation HRA methods are considered focusing on a couple of promising HRA methods, i.e., ATHEANA and CREAM, with the potential to assist the design review process. (author)

Effect of known clad and pellet reactions on the GEC ESL design of dry vault store

International Nuclear Information System (INIS)

Wheeler, D.

1984-01-01

The more important clad and pellet reactions and their temperature dependence are briefly reviewed, followed by an outline of the economical GEC ESL interim spent fuel storage concept that highlights: The ability of the concept to reduce the temperature of the fuel to values where the clad and pellet reactions are minimal. The containment philosophy that enables any consequences of the reactions to be safely retained to ALARA principles. The maintenance of an air storage environment that can never be lost. The utilisation of passive, naturally induced cooling regimes. The ability to continuously monitor for long-term degradation, together with ease of inspection at any time during storage

A simplified ALARA approach to demonstration of compliance with surface contaminated object regulatory requirements

International Nuclear Information System (INIS)

Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Boyle, R.W.; Cook, J.C.

1998-02-01

The US Department of Transportation (DOT) and the US Nuclear Regulatory Commission (NRC) have jointly prepared a comprehensive set of draft guidance for consignors and inspectors to use when applying the newly imposed regulatory requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). The guidance is being developed to facilitate compliance with the new LSA material and SCO requirements, not to impose additional requirements. These new requirements represent, in some areas, significant departures from the manner in which packaging and transportation of these materials and objects were previously controlled. On occasion, it may be appropriate to use conservative approaches to demonstrate compliance with some of the requirements, ensuring that personnel are not exposed to radiation at unnecessary levels, so that exposures are kept as low as reasonably achievable (ALARA). In the draft guidance, one such approach would assist consignors preparing a shipment of a large number of SCOs in demonstrating compliance without unnecessarily exposing personnel. In applying this approach, users need to demonstrate that four conditions are met. These four conditions are used to categorize non-activated, contaminated objects as SCO-2. It is expected that, by applying this approach, it will be possible to categorize a large number of small contaminated objects as SCO-2 without the need for detailed, quantitative measurements of fixed, accessible contamination, or of total (fixed and non-fixed) contamination on inaccessible surfaces. The method, which is based upon reasoned argument coupled with limited measurements and the application of a sum of fractions rule, is described and examples of its use are provided

FINAL DESIGN REVIEW REPORT Subcritical Experiments Gen 2, 3-ft Confinement Vessel Weldment

Energy Technology Data Exchange (ETDEWEB)

Romero, Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-28

A Final Design Review (FDR) of the Subcritical Experiments (SCE) Gen 2, 3-ft. Confinement Vessel Weldment was held at Los Alamos National Laboratory (LANL) on September 14, 2017. The review was a focused review on changes only to the confinement vessel weldment (versus a system design review). The changes resulted from lessons-learned in fabricating and inspecting the current set of confinement vessels used for the SCE Program. The baseline 3-ft. confinement vessel weldment design has successfully been used (to date) for three (3) high explosive (HE) over-tests, two (2) fragment tests, and five (5) integral HE experiments. The design team applied lessons learned from fabrication and inspection of these vessel weldments to enhance fit-up, weldability, inspection, and fitness for service evaluations. The review team consisted of five (5) independent subject matter experts with engineering design, analysis, testing, fabrication, and inspection experience. The

Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

International Nuclear Information System (INIS)

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant's or licensee's HSI design

Human reliability analysis in the man-machine interface design review

International Nuclear Information System (INIS)

Kim, I.S.

2001-01-01

Advanced, computer-based man-machine interface (MMI) is emerging as part of the new design of nuclear power plants. The impact of advanced MMI on the operator performance, and as a result, on plant safety should be thoroughly evaluated before such technology is actually adopted in the plants. This paper discusses the applicability of human reliability analysis (HRA) to support the design review process. Both the first-generation and the second-generation HRA methods are considered focusing on a couple of promising HRA methods, i.e. ATHEANA and CREAM, with the potential to assist the design review process

Design, test and start up of a cleaning system for the moderator tank bottom of Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Duca, J.; Gerber, O.; Ibero, M.; Riga, N.

1989-01-01

In order to perform the cleaning of the moderator tank bottom, during the repair of the Atucha I nuclear power plant (CNA I) failure, the Empresa Nuclear Argentina de Centrales Electricas (ENACE S.A.) designed a system with the following requirements (asked by CNA I): a) To aspirate and retain free solid particles, uranium dioxide pellets and coolant channels isolations (foils) of minor size settled at the moderator tank bottom, being the reactor at middle loop state. b) To allow a radially cleaning up to 1.4 m from the extracted channel. c) To design a lay-out attaining the ALARA dose exposure. The designed system basically consists in: a) Flexible intake for suction: allows the movement inside the moderator tank and provides the adequate speed to raise the particles. b) Filter: retains the aspirated particles, pellets and foils. Its capacity is 1.8 dm 3 and the minimum size of retained particles is 200 m. The ALARA dose exposure concept is attained due to that the filter is located inside the moderator tank. c) Filtering column: contains the filter and allows the entrance of the extraction and exchange tool (for the flexible intake and filter). d) Suction hose: connects the filtering column with the pump. Its flexibility allows its use in any channel maintaining the same positions of the discharge pump and the return piping. e) Discharge pump: it is a canned centrifugal pump with low-low net positive suction head. f) Return piping: discharges the filtered water into the moderator tank. The system fulfilled satisfactorily all requirements during its operation. (Author)

Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.

Human-centred design in global health: A scoping review of applications and contexts.

Directory of Open Access Journals (Sweden)

Alessandra N Bazzano

Full Text Available Health and wellbeing are determined by a number of complex, interrelated factors. The application of design thinking to questions around health may prove valuable and complement existing approaches. A number of public health projects utilizing human centered design (HCD, or design thinking, have recently emerged, but no synthesis of the literature around these exists. The results of a scoping review of current research on human centered design for health outcomes are presented. The review aimed to understand why and how HCD can be valuable in the contexts of health related research. Results identified pertinent literature as well as gaps in information on the use of HCD for public health research, design, implementation and evaluation. A variety of contexts were identified in which design has been used for health. Global health and design thinking have different underlying conceptual models and terminology, creating some inherent tensions, which could be overcome through clear communication and documentation in collaborative projects. The review concludes with lessons learned from the review on how future projects can better integrate design thinking with global health research.

Isotope Production Facility Conceptual Thermal-Hydraulic Design Review and Scoping Calculations

International Nuclear Information System (INIS)

Pasamehmetoglu, K.O.; Shelton, J.D.

1998-01-01

The thermal-hydraulic design of the target for the Isotope Production Facility (IPF) is reviewed. In support of the technical review, scoping calculations are performed. The results of the review and scoping calculations are presented in this report

Applying risk insights in US NRC reviews of integral pressurized water reactor designs

International Nuclear Information System (INIS)

Caruso, M.A.; Hilsmeier, T.; Kevern, T.A.

2012-01-01

In its Staff Requirements Memorandum (SRM) on COMGBJ-10-0004/COMGEA-10-0001, 'Use of Risk Insights to Enhance Safety Focus of Small Modular Reactor Reviews,' dated August 31, 2010 (ML102510405), the U.S. Nuclear Regulatory Commission (NRC) directed the NRC staff to more fully integrate the use of risk insights into pre-application activities and the review of small modular reactor (SMR) applications with near-term focus on integral pressurized water reactor (iPWR) designs. The Commission's objective is to align the review focus and resources with the risk-significant systems, structures, and components (SSCs) and other aspects of the design, that contribute most to safety in order to enhance the efficiency of the review process while still enabling a decision of reasonable assurance of the design's safety. The staff was directed to develop a design-specific, risk-informed review plan for each SMR to address pre-application and application review activities. The NRC staff submitted a response to the Commission which describes its approach for (1) using risk insights, consistent with current regulatory requirements, to assign SSCs to one of a limited set of graded categories, and (2) adjusting the scope and depth of current review plans--where possible--consistent with regulatory requirements and consistent with the applicable graded category. Because the staff's review constitutes an independent audit of the application, the staff may emphasize or de-emphasize particular aspects of its review guidance (i.e., Standard Review Plan), as appropriate and consistent with regulatory requirements, for the application being reviewed. The staff may propose justifications for not performing certain sections of the reviews called for by the applicable review plan. Examples of acceptable variations in the scope of a review can include reduced emphasis on SSC attributes such as reliability, availability, or functional performance when the SSC will be in the scope of a program

Guidelines on how to meet the requirement to keep all exposures as low as reasonably achievable. Regulatory guide

International Nuclear Information System (INIS)

1997-01-01

The purpose of Regulatory Guide G-129 (E) is to provide Atomic Energy Control Board (AECB) licensees with guidelines on how to meet the forthcoming AECB regulatory requirement to keep doses received by workers and members of the public As Low As Reasonably Achievable (ALARA), social and economic factors taken into account. it is realized that the scope for realistic dose reductions will vary depending on the nature of the licensed activity. Therefore, criteria are given in section D for determining if doses can be deemed to be as low as reasonably achievable without further evaluation. The elements that the AECB considers to be essential in the approach to ALARA are described in section E and are summarized as follows: a demonstrated management commitment to the ALARA principle; the implementation of ALARA through a licensee's organization and management, provision of resources, training, establishment of action levels, documentation and other measures; and regular operational reviews. The above elements will be the focus of any AECB assessment to verify compliance with the requirement to keep radiation exposures as low as reasonably achievable. (author)

Human factors design review guidelines for advanced nuclear control room technologies

International Nuclear Information System (INIS)

O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

Practice and experience of radiation protection and optimization (ALARA) management system in Daya Bay NPP during the past 10 years

International Nuclear Information System (INIS)

Chen Degan; He Yu; Yang Maochun; Gu Jingzhi

2004-01-01

With the practice of 10 years safe operation, Daya Bay Nuclear Power Station has established and continuously improved the management system for radiation protection and optimization (ALARA) which contains 3 basic requirements: all workers are trained, all employees are engaged in totally, and work management is implemented for the whole process. At the same time, strong efforts have been made to build the 'infrastructure' as a platform for its effective operation. This article introduces the contents and characteristics of the system and basic experiences of its effective implementation. In order to implement the management system effectively, it is necessary for NPPs to strengthen the responsibility system for radiation protection and the leading role of the radiation protection personnel, especially the role of technical support and supervision during the work with high radiation risk, emphasize the organic combination and actively mutual action with the safe operation management system of the plant, and pay great attention to the formation of safety culture and the experience feedback to ensure the continuous improvement of the management system

Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

Energy Technology Data Exchange (ETDEWEB)

O`Hara, J.M.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J. [Carlow International Inc., Falls Church, VA (United States)

1994-07-01

Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

International Nuclear Information System (INIS)

O'Hara, J.M.; Brown, W.S.; Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J.

1994-07-01

Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

Review on JMTR safety design for LEU core conversion

International Nuclear Information System (INIS)

Komori, Yoshihiro; Yokokawa, Makoto; Saruta, Toru; Inada, Seiji; Sakurai, Fumio; Yamamoto, Katsumune; Oyamada, Rokuro; Saito, Minoru

1993-12-01

Safety of the JMTR was fully reviewed for the core conversion to low enriched uranium fuel. Fundamental policies for the JMTR safety design were reconsidered based on the examination guide for safety design of test and research reactors, and safety of the JMTR was confirmed. This report describes the safety design of the JMTR from the viewpoint of major functions for reactor safety. (author)

Development of human factors design review guidelines(II)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

1998-06-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 11 refs., 2 figs., 2 tabs.

Recent perspectives on optimisation of radiological protection

International Nuclear Information System (INIS)

Robb, J.D.; Croft, J.R.

1992-01-01

The ALARA principle as a requirement in radiological protection has evolved from its theoretical roots. Based on several years work, this paper provides a backdrop to practical approaches to ALARA for the 1990s. The key step, developing ALARA thinking so that it becomes an integral part of radiological protection programmes, is discussed using examples from the UK and France, as is the role of tools to help standardise judgements for decision-making. In its latest recommendations, ICRP have suggested that the optimisation of protection should be constrained by restrictions on the doses to individuals. This paper also considers the function of such restrictions for occupational, public and medical exposure, and in the design process. (author)

Human-factors engineering-control-room design review: Shoreham Nuclear Power Station. Draft audit report

International Nuclear Information System (INIS)

Peterson, L.R.; Preston-Smith, J.; Savage, J.W.; Rousseau, W.F.

1981-01-01

A human factors engineering preliminary design review of the Shoreham control room was performed at the site on March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The presented sections are numbered to conform to the guidelines of the draft version of NUREG-0700. They summarize the teams's observations of the control room design and layout, and of the control room operators' interface with the control room environment

Final design of the generic upper port plug structure for ITER diagnostic systems

Energy Technology Data Exchange (ETDEWEB)

Pak, Sunil, E-mail: paksunil@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Feder, Russell [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Giacomin, Thibaud; Guirao, Julio; Iglesias, Silvia; Josseaume, Fabien [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Kalish, Michael; Loesser, Douglas [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Maquet, Philippe [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Ordieres, Javier; Panizo, Marcos [NATEC, Ingenieros, Gijón (Spain); Pitcher, Spencer; Portalès, Mickael [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Proust, Maxime [CEA, Cadarache, St. Paul-lez-Durance (France); Ronden, Dennis [FOM Institute DIFFER, Nieuwegein (Netherlands); Serikov, Arkady [Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen (Germany); Suarez, Alejandro [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Tanchuk, Victor [NIIEFA, St.-Petersburg (Russian Federation); Udintsev, Victor; Vacas, Christian [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); and others

2016-01-15

The generic upper port plug (GUPP) structure in ITER is a 6 m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which has successfully passed the final design review in 2013, is described here. The diagnostic port plug is cantilevered to the vacuum vessel with a heavy payload at the front, so called the diagnostic first wall (DFW) and the diagnostic shield module (DSM). Most of electromagnetic (EM) load (∼80%) occurs in DFW/DSM. Therefore, the mounting design to transfer the EM load from DFW/DSM to the GUPP structure is challenging, which should also comply with thermal expansion and tolerance for assembly and manufacturing. Another key design parameter to be considered is the gap between the port plug and the vacuum vessel port. The gap should be large enough to accommodate the remote handling of the heavy port plug (max. 25 t), the structural deflection due to external loads and machine assembly tolerance. At the same time, the gap should be minimized to stop the neutron streaming according to the ALARA (as low as reasonably achievable) principle. With these design constraints, the GUPP structure should also provide space for diagnostic integration as much as possible. This requirement has led to the single wall structure having the gun-drilled water channels inside the structure. Furthermore, intensive efforts have been made on the manufacturing study including material selection, manufacturing codes and French regulation related to nuclear equipment and safety. All these main design and manufacturing aspects are discussed in this paper, including requirements, interfaces, loads and structural assessment and maintenance.

Development of human factors design review guidelines(III)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1999-02-15

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

Development of human factors design review guidelines(III)

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1999-02-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines(II)

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1998-06-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines(III)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1999-02-15

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

Review of occupational radiation exposures in all biennial shutdown maintenance of Kaiga generating station

International Nuclear Information System (INIS)

Murukan, E.K.; Vinod Kumar, T.; Austine, N.X.; Soumia Menon, M.; Girish Kumar, K.; Rao, M.M.L.N.; Venkataramana, K.

2008-01-01

Full text: Kaiga generating station 1 and 2 consists of twin units of 220 M We pressurized heavy water reactors located in Karnataka, India. Major maintenance activities of one of the twin units are taken up once in two years (biennial shutdown) to execute system maintenance, system up gradation, surveillance and in-service inspection (ISI) jobs. BSDs are mandatory activities to comply with regulatory requirement to ensure the safety and reliability of plant system equipment. More than 65% of the station collective dose is contributed by biennial shutdown (BSD) jobs. It is observed that the man rem consumed during normal operation of the plant is less than 35% of the total man rem consumed. Since BSD jobs contributes significantly to station collective dose, an effective implementation of radiation protection programme specific to BSD is the key to control the occupational exposure. Various improvements in the field of radiation protection practices and process systems are adopted to achieve lowest collective dose at par with international standards. The key areas identified for application of various strategies to achieve ALARA were Man rem budgeting, Radiological condition monitoring, Radiation protection practices, Identification of critical jobs and Work groups, Work planning and execution, and Radioactive waste management. Review of collective doses of all the BSD jobs performed in the station since year 2004 and various measures incorporated to achieve ALARA exposures to plant personnel are briefly discussed in this paper. (author)

Review of FFTF and CRBRP control rod systems designs

International Nuclear Information System (INIS)

Pitterle, T.A.; Lagally, H.O.

1977-01-01

The evolution of the primary control rod system design for FFTF and CRBR, beginning with the initial choice of the basic concepts, is described. The significant component and systems tests are reviewed together with the test results which referenced the development of the CRBR primary control rod system design. Modifications to the concepts and detail designs of the FFTF control rod system were required principally to satisfy the requirements of CRBR, and at the same time incorporating design refinements shown desirable by the tests

GCRA review and appraisal of HTGR reactor-core-design program

International Nuclear Information System (INIS)

1980-09-01

The reactor-core-design program has as its principal objective and responsibility the design and resolution of major technical issues for the reactor core and core components on a schedule consistent with the plant licensing and construction program. The task covered in this review includes three major design areas: core physics, core thermal and hydraulic performance fuel element design, and in-core fuel performance evaluation

Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

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

A review of electronic engineering design free software tools

OpenAIRE

Medrano Sánchez, Carlos; Plaza García, Inmaculada; Castro Gil, Manuel Alonso; García Sevilla, Francisco; Martínez Calero, J.D.; Pou Félix, Josep; Corbalán Fuertes, Montserrat

2010-01-01

In this paper, we review electronic design free software tools. We have searched open source programs that help with several tasks of the electronic design flow: analog and digital simulation, schematic capture, printed circuit board design and hardware description language compilation and simulation. Using some rapid criteria for verifying their availability, we have selected some of them which are worth working with. This work intends to perform a deeper analysis of fre...

Human-factors engineering control-room design review/audit report: Byron Generating Station, Commonwealth Edison Company

International Nuclear Information System (INIS)

Savage, J.W.

1983-01-01

A human factors engineering design review/audit of the Byron Unit 1 control room was performed at the site on November 17 through November 19, 1981. This review was accomplished using the Unit 2 control room appropriately mocked-up to reflect design changes already committed to be incorporated in Unit 1. The report was prepared on the basis of the HFEB's audit of the applicant's Preliminary Design Assessment report and the human factors engineering design review performed at the site. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. The review team was assisted by consultants from BioTechnology, Inc. (Falls Church, Virginia), and from Lawrence Livermore National Laboratory (University of California), Livermore, California

Position paper - peer review and design verification of selected activities

International Nuclear Information System (INIS)

Stine, M.D.

1994-09-01

Position Paper to develop and document a position on the performance of independent peer reviews on selected design and analysis components of the Title I (preliminary) and Title II (detailed) design phases of the Multi-Function Waste Tank Facility project

DSRS guidelines. Reference document for the IAEA Design Safety Review Services

International Nuclear Information System (INIS)

1999-01-01

The publication covers the general topic of design safety review of a nuclear power plant. It is intended to make Member States aware of the possibility of a service through which they can have a better appreciation of the overall design of a facility or of a plant already in operation. It includes a generic and procedural part followed by a technical part corresponding to different systems of a nuclear power plant. It is intended to be used mainly in preparation and execution of a design review service by the IAEA and to provide information to potential recipients of the service regarding the effort involved and the topics that can be covered. it is expected to be useful if Member States decide to conduct such reviews themselves either through regulatory authorities or as part of self assessment activities by plant management

Designed graphene-peptide nanocomposites for biosensor applications: A review

International Nuclear Information System (INIS)

Wang, Li; Zhang, Yujie; Wu, Aiguo; Wei, Gang

2017-01-01

The modification of graphene with biomacromolecules like DNA, protein, peptide, and others extends the potential applications of graphene materials in various fields. The bound biomacromolecules could improve the biocompatibility and bio-recognition ability of graphene-based nanocomposites, therefore could greatly enhance their biosensing performances on both selectivity and sensitivity. In this review, we presented a comprehensive introduction and discussion on recent advance in the synthesis and biosensor applications of graphene-peptide nanocomposites. The biofunctionalization of graphene with specifically designed peptides, and the synthesis strategies of graphene-peptide (monomer, nanofibrils, and nanotubes) nanocomposites were demonstrated. On the other hand, the fabrication of graphene-peptide nanocomposite based biosensor architectures for electrochemical, fluorescent, electronic, and spectroscopic biosensing were further presented. This review includes nearly all the studies on the fabrication and applications of graphene-peptide based biosensors recently, which will promote the future developments of graphene-based biosensors in biomedical detection and environmental analysis. - Highlights: • A comprehensive review on the fabrication and application of graphene-peptide nanocomposites was presented. • The design of peptide sequences for biofunctionalization of various graphene materials was presented. • Multi-strategies on the fabrication of biosensors with graphene-peptide nanocomposites were discussed. • Designed graphene-peptide nanocomposites showed wide biosensor applications.

The role of work management in occupational dose control

International Nuclear Information System (INIS)

Coates, R.; Lefaure, C.; Schieber, C.

1993-01-01

ALARA is an important and growing part of radiological protection practice and it is clear that the management approach adopted towards radiation work can have a major influence over the degree of radiation exposure in the workplace. This paper reviews the various contributors to work management relating to the achievement of ALARA. It first addresses the institutional arrangements such as the regulatory framework, company organization and people motivation factors. The paper then considers the management of the tasks themselves and looks at how the lesson learned can be assessed and made available to a wider audience, and indeed whether it is possible to quantify the key parameters in order to aid the prediction of future exposures. Finally it outlines the key questions in the field of ALARA work management with the objective of focusing future discussions

Design review report for modifications to RMCS safety class equipment

International Nuclear Information System (INIS)

Corbett, J.E.

1997-01-01

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable

Design review report for modifications to RMCS safety class equipment

Energy Technology Data Exchange (ETDEWEB)

Corbett, J.E.

1997-05-30

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

Shielding design for the target room of the proton accelerator research center

International Nuclear Information System (INIS)

Min, Y. S.; Lee, C. W.; Mun, K. J.; Nam, J.; Kim, J. Y.

2010-01-01

The Proton Engineering Frontier Project (PEFP) has been developing a 100-MeV proton linear accelerator. Also, PEFP has been designing the Proton Accelerator Research Center (PARC). In the Accelerator Tunnel and Beam Experiment Hall in PARC, 10 target rooms for the 20- and 100-MeV beamline facilities exist in the Beam Experiment Hall. For the 100-MeV target rooms during 100-MeV proton beam extraction, a number of high energy neutrons, ranging up to 100-MeV, are produced. Because of the high beam current and space limitations of each target room, the shielding design of each target room should be considered seriously. For the shielding design of the 100-MeV target rooms of the PEFP, a permanent and removable local shield structure was adopted. To optimize shielding performance, we evaluated four different shield materials (concrete, HDPE, lead, iron). From the shielding calculation results, we confirmed that the proposed shielding design made it possible to keep the dose rate below the 'as low as reasonably achievable (ALARA)' objective.

Review of public comments on proposed seismic design criteria

International Nuclear Information System (INIS)

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

1989-01-01

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

The design of reliability data bases, part I: review of standard design concepts

International Nuclear Information System (INIS)

Cooke, Roger M.

1996-01-01

Main styles in the design of reliability data banks (RDB's) are reviewed. The conceptual and mathematical tools underlying these designs are summarized. A key point is the method for assessing failure rates for competing failure modes. The theory of independent competing risk and the relation to colored Poisson processes is explained. The notions of observed and naked failure rates are defined, and their equivalence under the assumption of independence is shown. In conclusion, the needs of different users are compared with the information currently offered

Review of revised Japanese seismic guidelines for Nuclear Power Plant design

International Nuclear Information System (INIS)

Kato, M.

1987-01-01

Development of aseismic design for nuclear power plants in Japan has evolved roughly in three stages. The first phase, which continued by 1978, was a period progressive development when design for each siteplant has referred to designs of predecessor plants and have added the latest knowledge and experience in that time. The second phase from issuance of 'Regulatory Guide for Aseismic Design of Nuclear Power Reactor Facilities' (1978, revised in 1981), or 1978 to 1986, was a period when the application of customary conservative design method was continued, while standardization of the aseismic design technology have been proceded. It is in this phase when new knowledge was accumulated by aseismic proof studies. The third phase represents a transient period to rational design when the conservative aseismic design technology has been reviewed due to the new knowledge and revision of the above JEAG guideline has progressed for incorporation in design, and ont the other hand by-laws of the Ministry of International Trade and Industry are being provided. In this report a review is given of aseismic design and its guideline after the second phase onward and an overview of the revised JEAG - Recent Aseismic Design Method - and the by-laws including rationalization of aseismic design technology

Residential Solar Design Review: A Manual on Community Architectural Controls and Solar Energy Use.

Science.gov (United States)

Jaffe, Martin; Erley, Duncan

Presented are architectural design issues associated with solar energy use, and procedures for design review committees to consider in examining residential solar installation in light of existing aesthetic goals for their communities. Recommended design review criteria include the type of solar system being used and the ways in which the system…

A Critical Review of Instructional Design Process of Distance Learning System

Science.gov (United States)

Chaudry, Muhammad Ajmal; ur-Rahman, Fazal

2010-01-01

Instructional design refers to planning, development, delivery and evaluation of instructional system. It is an applied field of study aiming at the application of descriptive research outcomes in regular instructional settings. The present study was designed to critically review the process of instructional design at Allama Iqbal Open University…

NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

Energy Technology Data Exchange (ETDEWEB)

Levin, A.E.

1995-09-01

New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

Design review report FFTF interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1995-01-01

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

Utilizing occupational exposure data to improve system design

International Nuclear Information System (INIS)

Cook, A.

1980-01-01

Designers of nuclear fuel cycle facilities are now faced with the difficult task of complying with the ICRP recommendation that all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account. This recommendation has parallels in English factory law, in which obligations are frequently qualified by the phrase ''so far as reasonably practicable'', and there is extensive experience of determining what is reasonably practicable in particular circumstances. This experience is summarized and observations made of the application of the concept ''reasonably practicable'' as a basis for understanding how the ALARA concept might be applied. The view is expressed that, in the greater part, optimization is a matter for observation and comparison rather than for theoretical calculation. If this view is accepted, it will be necessary for health physicists to consider how their attempts to keep doses as low as reasonably achievable might be presented for use by designers of the next generation of nuclear fuel cycle facilities. Also, international agreement should be reached on a common approach to data presentation and retrieval. (author)

Formal design review report project W-151 mixer pump procurement

Energy Technology Data Exchange (ETDEWEB)

Crass, D.W.

1997-01-21

A formal design review for WHC-S-0040 was held on January 21, 1993. The review was completed January 29, 1993. No outstanding action items existed. Comments were recorded on Record Comment Record (RCR) forms and incorporated into the specification. The specification was considered acceptable, approved and issued as WHC-S-0040, Rev. 0 on March 4, 1993.

Review of Y/OWI/TM-36: repository design performance in salt, granite, shale or basalt

International Nuclear Information System (INIS)

Talbot, R.; Nair, O.B.

1979-09-01

As part of the ongoing work by the Lawrence Livermore Laboratory to evaluate repository design performance, this memorandum presents a review of the preconceptual repository design described in Y/OWI/TM-36, Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, April 1978. The purpose of this review is: to assess the adequacy of the design procedures and assumptions; to identify inappropriate or unsubstantiated design issues; to identify areas where additional numerical analyses may be required; and to develop data for inclusion in a reference repository design. The preconceptual repository design is presented in the form of 23 volumes of data base, analyses, and design layouts for four rock types: bedded salt, shale, granite and basalt. This memorandum reviews all four repository designs

Review of high fidelity imaging spectrometer design for remote sensing

Science.gov (United States)

Mouroulis, Pantazis; Green, Robert O.

2018-04-01

We review the design and assessment techniques that underlie a number of successfully deployed space and airborne imaging spectrometers that have been demonstrated to achieve demanding specifications in terms of throughput and response uniformity. The principles are illustrated with telescope designs as well as spectrometer examples from the Offner and Dyson families. We also show how the design space can be extended with the use of freeform surfaces and provide additional design examples with grating as well as prism dispersive elements.

Considerations concerning the Alara principle, the α value, and the Choice of attributes

International Nuclear Information System (INIS)

Sordi, G. M.

2004-01-01

The paper initially introduces the ALARA principle conceptually through its equations which demand the maximum net benefit, and consecutively demonstrates that it can be interpreted as discriminator between the radiation protection options which are to be avoided and those which are allowed. With respect to the alpha value, the paper demonstrates that it can be interpreted as an indicator of the velocity decrease of the involved doses. If the entities involved, that which contributes to the protection costs, and that which contributes to the detriment cost are different, substantial inequities could be committed if certain indispensable precautions are not taken. When the quantitative decision-aiding techniques are used in the analysis, these being; the multi-attribute utility analysis, or the multicriteria outranking analysis, a larger number of attributes are permitted in addition to the two obligatory attributes of protection cost and detriment cost. With this approach it is observed that those attributes which decrease when the annual protection costs increase (or the annual collective dose decreases), tends to increase the alpha value and viceversa. This phenomena leads us to various conclusions such as: a) if the quantitative decision-aiding techniques of cost-benefit, differential cost-benefit, and extended cost benefit are employed the alpha value is explicit, and therefore can be argued between the involved parties. However if the more complex quantitative analyses are used, the selection of the attributes can substantially increase or decrease the alpha value, committing inequity to one of the parties involved in benefit to the other; b) in order to avoid large distortions provoked by the use of non-obligatory attributes, these should be weighted in such a manner that the decrease provoked by some should be compensated by the increase caused by the use of non-obligatory attributes, these should be weighted in such a manner that the decrease caused by some

Considerations concerning the Alara principle, the {alpha} value, and the Choice of attributes

Energy Technology Data Exchange (ETDEWEB)

Sordi, G. M.

2004-07-01

The paper initially introduces the ALARA principle conceptually through its equations which demand the maximum net benefit, and consecutively demonstrates that it can be interpreted as discriminator between the radiation protection options which are to be avoided and those which are allowed. With respect to the alpha value, the paper demonstrates that it can be interpreted as an indicator of the velocity decrease of the involved doses. If the entities involved, that which contributes to the protection costs, and that which contributes to the detriment cost are different, substantial inequities could be committed if certain indispensable precautions are not taken. When the quantitative decision-aiding techniques are used in the analysis, these being; the multi-attribute utility analysis, or the multicriteria outranking analysis, a larger number of attributes are permitted in addition to the two obligatory attributes of protection cost and detriment cost. With this approach it is observed that those attributes which decrease when the annual protection costs increase (or the annual collective dose decreases), tends to increase the alpha value and viceversa. This phenomena leads us to various conclusions such as: a) if the quantitative decision-aiding techniques of cost-benefit, differential cost-benefit, and extended cost benefit are employed the alpha value is explicit, and therefore can be argued between the involved parties. However if the more complex quantitative analyses are used, the selection of the attributes can substantially increase or decrease the alpha value, committing inequity to one of the parties involved in benefit to the other; b) in order to avoid large distortions provoked by the use of non-obligatory attributes, these should be weighted in such a manner that the decrease provoked by some should be compensated by the increase caused by the use of non-obligatory attributes, these should be weighted in such a manner that the decrease caused by some

A corporate ALARA engineering support for all EDF nuclear power plan

Energy Technology Data Exchange (ETDEWEB)

Quiot, A.; Orjol, A. [Electricite de France (EDF/UTO), 93 - Noisy le Grand (France); Lafferriere, F.; Fraissinet, E. [Electricite de France (EDF-CNPE) du Blayais, 33 - Saint Ciers sur Gironde (France)

2006-07-01

Since 1991, EDF has established a national ALARA programme with a very effective result in terms of dose reduction. Of course, EDF management has decided to further improve occupational exposure management and dose reduction (both collective and individuals). Since 2002, one key element allowing reaching the new goals, is the set up of a national corporate engineering as a support for EDF sites for preparing maintenance interventions. Its objective is to reduce occupational exposure with the help of up to date tools and methods. That engineering support consists of a growing up team comprising at the moment about ten engineers, including CAD specialists and health physicists. It is in charge of using very efficient tools such as P.A.N.T.H.E.R. -R.P. to perform national modelling studies concerning the reactor and auxiliary buildings areas, which are the most costly in terms of doses. That tool has been developed initially for the first steam generator replacements by EDF S.E.P.T.E.N. engineering department. It uses friendly user 3D software to create a geometrical model of the concerned area with all existing materials (pipes, valves, concrete walls allowing visualizing on personal computers, each area from all perspectives. Other important inputs for P.A.N.T.H.E.R. R.P. are the quantities of radioisotopes present in each material. The code allows then estimating the dose rates at each location in the area, calculating the contribution of each equipment (i.e sources) in the area to the dose rate in each point; calculating also the contribution of each radio isotope to the dose rates. With the help of these models the engineering is then able to perform in depth generic work areas optimisation studies, taking into account the workload in each workstation. Up to recently these studies were performed only for huge operations such as steam generator replacements, they are now proposed to EDF sites for more usual interventions. The selection of these interventions takes

A corporate ALARA engineering support for all EDF nuclear power plan

International Nuclear Information System (INIS)

Quiot, A.; Orjol, A.; Lafferriere, F.; Fraissinet, E.

2006-01-01

Since 1991, EDF has established a national ALARA programme with a very effective result in terms of dose reduction. Of course, EDF management has decided to further improve occupational exposure management and dose reduction (both collective and individuals). Since 2002, one key element allowing reaching the new goals, is the set up of a national corporate engineering as a support for EDF sites for preparing maintenance interventions. Its objective is to reduce occupational exposure with the help of up to date tools and methods. That engineering support consists of a growing up team comprising at the moment about ten engineers, including CAD specialists and health physicists. It is in charge of using very efficient tools such as P.A.N.T.H.E.R. -R.P. to perform national modelling studies concerning the reactor and auxiliary buildings areas, which are the most costly in terms of doses. That tool has been developed initially for the first steam generator replacements by EDF S.E.P.T.E.N. engineering department. It uses friendly user 3D software to create a geometrical model of the concerned area with all existing materials (pipes, valves, concrete walls allowing visualizing on personal computers, each area from all perspectives. Other important inputs for P.A.N.T.H.E.R. R.P. are the quantities of radioisotopes present in each material. The code allows then estimating the dose rates at each location in the area, calculating the contribution of each equipment (i.e sources) in the area to the dose rate in each point; calculating also the contribution of each radio isotope to the dose rates. With the help of these models the engineering is then able to perform in depth generic work areas optimisation studies, taking into account the workload in each workstation. Up to recently these studies were performed only for huge operations such as steam generator replacements, they are now proposed to EDF sites for more usual interventions. The selection of these interventions takes

Interactive augmented reality system for product design review

Science.gov (United States)

Caruso, Giandomenico; Re, Guido Maria

2010-01-01

The product development process, of industrial products, includes a phase dedicated to the design review that is a crucial phase where various experts cooperate in selecting the optimal product shape. Although computer graphics allows us to create very realistic virtual representations of the products, it is not uncommon that designers decide to build physical mock-ups of their newly conceived products because they need to physically interact with the prototype and also to evaluate the product within a plurality of real contexts. This paper describes the hardware and software development of our Augmented Reality design review system that allows to overcome some issues related to the 3D visualization and to the interaction with the virtual objects. Our system is composed by a Video See Through Head Mounted Display, which allows to improve the 3D visualization by controlling the convergence of the video cameras automatically, and a wireless control system, which allows us to create some metaphors to interact with the virtual objects. During the development of the system, in order to define and tune the algorithms, we have performed some testing sessions. Then, we have performed further tests in order to verify the effectiveness of the system and to collect additional data and comments about usability and ergonomic aspects.

Review of ASME-NH Design Materials for Creep-Fatigue

International Nuclear Information System (INIS)

Koo, Gyeong Hoi; Kim, Jong Bum

2010-01-01

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

Controlling occupational radiation exposure at operating nuclear power stations

International Nuclear Information System (INIS)

Dickson, H.W.; Oakes, T.W.; Shank, K.E.

1977-01-01

The historical development of the philosophy of keeping the radiation exposure of workers at light-water reactors as low as reasonably achievable (ALARA) is presented. A review is made of some of the ALARA activities of the Nuclear Regulatory Commission, the Energy Research and Development Administration, and various nuclear installations. Data compiled by the NRC show that routine and special maintenance at light-water reactors accounts for 72 percent of all occupational exposure at these sites. The role that Oak Ridge National Laboratory has taken in ALARA research is presented, with emphasis placed on a study of valve malfunctions at light-water reactors. The valve study indicates a trend toward decreasing valve reliability over the past few years. Finally a cost--benefit analysis of radiation dose reduction is discussed. The rationale for assigning a cost per man-rem based on the radiation exposure level that is encountered is presented

Cost effective radiation risk management in a generic nuclear plant design

International Nuclear Information System (INIS)

Maan, M.A.

1982-11-01

To determine whether any further dose reduction measures are justified, a method appropriate for cost effective radiation risk management has been developed. This new method is based on the radiation detriment optimization measures advocated in the revised (1977) ALARA concept. The methodology includes the determination of available alternatives, and the determination of the variable monetary ceiling on expenditures to reduce the radiological detriment (both occupational and public). The method used to determine the maximum justifiable expenditure for additional reduction of detriment takes into account the economic and social climate, administrative/legal exposure limits, and the actual magnitude of risk. All these factors may vary from country to country. The variable monetary ceiling, sensitive to an actual level of risk, provides a handy measure allowing designers to make a decision whether or not the modification of design is necessary and/or cost effective. This will ensure rationally and consistently that the utilities and their customers (public) get maximum benefit for their safety dollars

Fish-inspired robots: design, sensing, actuation, and autonomy--a review of research.

Science.gov (United States)

Raj, Aditi; Thakur, Atul

2016-04-13

Underwater robot designs inspired by the behavior, physiology, and anatomy of fishes can provide enhanced maneuverability, stealth, and energy efficiency. Over the last two decades, robotics researchers have developed and reported a large variety of fish-inspired robot designs. The purpose of this review is to report different types of fish-inspired robot designs based upon their intended locomotion patterns. We present a detailed comparison of various design features like sensing, actuation, autonomy, waterproofing, and morphological structure of fish-inspired robots reported in the past decade. We believe that by studying the existing robots, future designers will be able to create new designs by adopting features from the successful robots. The review also summarizes the open research issues that need to be taken up for the further advancement of the field and also for the deployment of fish-inspired robots in practice.

Radioprotection optimization in the electronuclear, industrial and medical domains

International Nuclear Information System (INIS)

Schieber, C.; Abela, G.; Ammerich, M.; Balduyck, S.; Batalla, A.; Drouet, F.; Fracas, P.; Gauron, Ch.; Le Guen, B.; Lombard, J.; Mougnard, Ph.; Murith, Ch.; Rannou, A.; Rodde, S.; Selva, M.; Tranchant, Ph.; Schieber, C.; Solaire, T.; Le Tonqueze, Y.; Jolivet, P.; Chauveau, D.; Mathevet, L.; Juhel, T.; Mertz, L.; Bochud, F.O.; Desmaris, G.; Turquet de Beauregard, G.; Roy, C.; Delacroix, S.; Sevilla, A.; Rehel, J.L.; Bernhard, S.; Palut-Laurent, O.; Lochard, J.; Lebaron-Jacobs, L.; Wack, G.; Barange, K.; Delabre, H.

2011-01-01

This document gathers the slides of the available presentations given during these conference days. Thirty one presentations are assembled in the document and deal with: 1 - implementation of the ALARA principle in the nuclear, industrial and medical domains: status and challenges (C. Schieber); 2 - image quality and scanner irradiation: what ingredients to chose? (T. Solaire); 3 - radioprotection stakes and implementation of the ALARA approach during the IFMIF design (Y. Le Tonqueze); 4 - ALARA at the design stage of the EPR (P. Jolivet); 5 - alternative techniques to iridium 192 gamma-graphy for welds control: results and recommendations from the ALTER-X project (D. Chauveau); 6 - alternative techniques to ionizing radiations use in the medical domain: implementation of navigation strategies (L. Mathevet); 7 - justification of ionizing radiations use in non-medical imaging: overview of the French situation and perspectives status (S. Rodde); 8 - ISOE: task scheduling for radioprotection optimization in nuclear power plants (G. Abela); 9 - Practices and ALARA prospects among big nuclear operators (T. Juhel); 10 - experience feedback on the use of diagnostic reference levels (DRLs) in diagnostic imaging optimization (L. Mertz); 11 - DRLs: Swiss strategy and concept limits (F.O. Bochud); 12 - external dosimetry tools: the existing, the developing and the remaining problems (A. Rannou); 13 - is the optimization principle applicable to the aircraft personnel's exposure to cosmic radiation? (G. Desmaris); 14-15 - experience feedback of the ALARA approach concerning an operation with strong dosimetric stakes (P. Mougnard and N. Fontaine); 16 - optimization of reactor pool decontaminations ((P. Tranchant); 17 - radiopharmaceuticals transport - ALARA principle related stakes (G. Turquet de Beauregard); 18 - ALARA in vet radio-diagnosis activity: good practices guide (C. Roy); 19 - implementation of the ALARA approach at the Proton-therapy centre of Orsay's Curie Institute

Radioprotection optimization in the electronuclear, industrial and medical domains; Optimisation de la radioprotection dans les domaines electronucleaire, industriel et medical

Energy Technology Data Exchange (ETDEWEB)

Schieber, C.; Abela, G.; Ammerich, M.; Balduyck, S.; Batalla, A.; Drouet, F.; Fracas, P.; Gauron, Ch.; Le Guen, B.; Lombard, J.; Mougnard, Ph.; Murith, Ch.; Rannou, A.; Rodde, S.; Selva, M.; Tranchant, Ph.; Schieber, C.; Solaire, T.; Le Tonqueze, Y.; Jolivet, P.; Chauveau, D.; Mathevet, L.; Juhel, T.; Mertz, L.; Bochud, F.O.; Desmaris, G.; Turquet de Beauregard, G.; Roy, C.; Delacroix, S.; Sevilla, A.; Rehel, J.L.; Bernhard, S.; Palut-Laurent, O.; Lochard, J.; Lebaron-Jacobs, L.; Wack, G.; Barange, K.; Delabre, H.

2011-07-01

This document gathers the slides of the available presentations given during these conference days. Thirty one presentations are assembled in the document and deal with: 1 - implementation of the ALARA principle in the nuclear, industrial and medical domains: status and challenges (C. Schieber); 2 - image quality and scanner irradiation: what ingredients to chose? (T. Solaire); 3 - radioprotection stakes and implementation of the ALARA approach during the IFMIF design (Y. Le Tonqueze); 4 - ALARA at the design stage of the EPR (P. Jolivet); 5 - alternative techniques to iridium 192 gamma-graphy for welds control: results and recommendations from the ALTER-X project (D. Chauveau); 6 - alternative techniques to ionizing radiations use in the medical domain: implementation of navigation strategies (L. Mathevet); 7 - justification of ionizing radiations use in non-medical imaging: overview of the French situation and perspectives status (S. Rodde); 8 - ISOE: task scheduling for radioprotection optimization in nuclear power plants (G. Abela); 9 - Practices and ALARA prospects among big nuclear operators (T. Juhel); 10 - experience feedback on the use of diagnostic reference levels (DRLs) in diagnostic imaging optimization (L. Mertz); 11 - DRLs: Swiss strategy and concept limits (F.O. Bochud); 12 - external dosimetry tools: the existing, the developing and the remaining problems (A. Rannou); 13 - is the optimization principle applicable to the aircraft personnel's exposure to cosmic radiation? (G. Desmaris); 14-15 - experience feedback of the ALARA approach concerning an operation with strong dosimetric stakes (P. Mougnard and N. Fontaine); 16 - optimization of reactor pool decontaminations ((P. Tranchant); 17 - radiopharmaceuticals transport - ALARA principle related stakes (G. Turquet de Beauregard); 18 - ALARA in vet radio-diagnosis activity: good practices guide (C. Roy); 19 - implementation of the ALARA approach at the Proton-therapy centre of Orsay's Curie

A Review Of Design And Control Of Automated Guided Vehicle Systems

NARCIS (Netherlands)

T. Le-Anh (Tuan); M.B.M. de Koster (René)

2004-01-01

textabstractThis paper presents a review on design and control of automated guided vehicle systems. We address most key related issues including guide-path design, estimating the number of vehicles, vehicle scheduling, idle-vehicle positioning, battery management, vehicle routing, and conflict

The design and application of effective written instructional material: a review of published work.

Science.gov (United States)

Mayberry, John F

2007-09-01

This review will consider the evidence base for the format of educational material drawing on academic papers and the practice of the design industry. The core issues identified from the review are drawn together in guidelines for educational posters, text and web based material. The review deals with the design of written material both for use in leaflets and books as well as the impact of factors such as font type and size as well as colour on poster design. It sets these aspects of educational material within a research framework, which looks at impact on learning and subsequent change in practice. These issues are examined through a practical example of a poster designed for a regional gastroenterology meeting.

Results of readiness review for start of Title II Design of ESF in salt

International Nuclear Information System (INIS)

1986-01-01

The Readiness Review Board recommends that the ESF Title II Design be initiated after approval of revised Functional Design Criteria for Title II design. This review was conducted assuming a Deaf Smith location for ESF. Seventy-four open items and eight technical holds were identified during the Readiness Review that must be addressed and resolved to ensure successful completion of the ESF Title II Design. These items include definition and approval of surface based, EDH, and subsurface testing requirements; development of an approved OCRWM/SRPO licensing position for the ESF; and acquisition and availability of site-specific confirmatory data. A Risk Assessment should be conducted to define corrective action data and technical, cost and schedule impacts and associated program risks of continuation of Title II design activities beyond those dates

ALARA Principle Application for Loading Spent Nuclear Fuel Assemblies from Nuclear Research Reactor WR-S Mergal-Bucharest Romania into Transportation Casks

International Nuclear Information System (INIS)

Dragusin, M.

2009-01-01

Safety implementation of Spent Nuclear Fuels Assemblies (SNFA) handling procedures at the WR-S reactor site is ensured by technical perfection and reliability of equipment, monitoring of its condition, qualification and discipline of personnel as well as organization and execution of work complied with requirements of regulatory documents, process procedures, guidance and manuals. The personnel training for execution loading of SNF FAs is other important aspect for radiation protection and safely activities. Estimations carried out using Micro Shield software show that maximal dose rate upon working site when loading four FAs into basket of cask will not exceed 1.7 and 956;Sv/h, excluding natural radiation. Radiation Safety Analyses estimates for loading 70 SNFA in 18 transportation casks are: maximal individual dose: 4274.7 and 956;Sv, maximal expected collective dose persons: 17 031.2 man and 956;Sv. By application ALARA principle with technical and administrative measures the loading process developed in the following conditions: maximal individual dose: 68 and 956;Sv, the collective dose persons: 732 man and 956;Sv. The work will presented the technical measures and procedures applied in loading process.

Product-oriented design theory for digital information services: A literature review.

NARCIS (Netherlands)

Wijnhoven, Alphonsus B.J.M.; Kraaijenbrink, Jeroen

2008-01-01

Purpose – The purpose of this paper is to give a structured literature review, design concepts, and research propositions related to a product-oriented design theory for information services. Information services facilitate the exchange of information goods with or without transforming these goods.

Human factors engineering review for CRT screen design

International Nuclear Information System (INIS)

Yi, S. M.; Joo, C. Y.; Ra, J. C.

1999-01-01

The information interface between man and machine may be more important than hardware and workplace layout considerations. Transmitting and receiving data through this information interface can be characterized as a communication or interface problem. Management of man-machine interface is essential for the enhancement of the information processing and decision-making capability of computer users working in real time, demanding task. The design of human-computer interface is not a rigid and static procedure. The content and context of each interface varies according to the specific application. So, the purpose of this study is to review the human factor design process for interfaces, to make human factor guidelines for CRT screen and to apply these to CRT screen design. (author)

Demystifying Mixed Methods Research Design: A Review of the Literature

OpenAIRE

Gail D. Caruth

2013-01-01

Mixed methods research evolved in response to the observed limitations of both quantitative and qualitative designs and is a more complex method. The purpose of this paper was to examine mixed methods research in an attempt to demystify the design thereby allowing those less familiar with its design an opportunity to utilize it in future research. A review of the literature revealed that it has been gaining acceptance among researchers, researchers have begun using mixed methods research, it ...

The poacher turned gamekeeper, or getting the most out of the design review process

Science.gov (United States)

Craig, Simon C.

2010-07-01

This paper presents an accumulation of knowledge from both sides of the design review table. Using experience gained over many reviews and post-mortems, some painful, some less painful; examining stakeholder's viewpoints and expectations; challenging aspects of accepted wisdom and posing awkward questions, the author brings out what he considers to be key criteria for a constructive design review. While this is not a guarantee to a successful outcome, it may nudge the balance from the reviews being an obligatory milestone (millstone?) towards them being a beneficial mechanism for project development.

Convergent and sequential synthesis designs: implications for conducting and reporting systematic reviews of qualitative and quantitative evidence.

Science.gov (United States)

Hong, Quan Nha; Pluye, Pierre; Bujold, Mathieu; Wassef, Maggy

2017-03-23

Systematic reviews of qualitative and quantitative evidence can provide a rich understanding of complex phenomena. This type of review is increasingly popular, has been used to provide a landscape of existing knowledge, and addresses the types of questions not usually covered in reviews relying solely on either quantitative or qualitative evidence. Although several typologies of synthesis designs have been developed, none have been tested on a large sample of reviews. The aim of this review of reviews was to identify and develop a typology of synthesis designs and methods that have been used and to propose strategies for synthesizing qualitative and quantitative evidence. A review of systematic reviews combining qualitative and quantitative evidence was performed. Six databases were searched from inception to December 2014. Reviews were included if they were systematic reviews combining qualitative and quantitative evidence. The included reviews were analyzed according to three concepts of synthesis processes: (a) synthesis methods, (b) sequence of data synthesis, and (c) integration of data and synthesis results. A total of 459 reviews were included. The analysis of this literature highlighted a lack of transparency in reporting how evidence was synthesized and a lack of consistency in the terminology used. Two main types of synthesis designs were identified: convergent and sequential synthesis designs. Within the convergent synthesis design, three subtypes were found: (a) data-based convergent synthesis design, where qualitative and quantitative evidence is analyzed together using the same synthesis method, (b) results-based convergent synthesis design, where qualitative and quantitative evidence is analyzed separately using different synthesis methods and results of both syntheses are integrated during a final synthesis, and (c) parallel-results convergent synthesis design consisting of independent syntheses of qualitative and quantitative evidence and an

ALARA and work management

International Nuclear Information System (INIS)

Schieber, C.; Perin, M.; Saumon, P.

1995-01-01

At the request of Electricite de France (EDF) and Framatome, the Nuclear Protection Evaluation Centre (CEPN) developed a three-year research project, between 1991 and 1993, to evaluate the impact of various work management factors that can influence occupational exposures in nuclear power plants (NPPs) and to assess the effectiveness of protective actions implemented to reduce them. Three different categories of factors have been delineated: those linked to working conditions (such as ergonomic of work areas and protective suits), those characterizing the operators (qualification, experience level, motivation, etc.). In order to quantify the impact of these factors, a detailed survey was carried out in five French NPPs, focusing on three types of operations: primary valves maintenance, decontamination of reactor cavity, and specialized maintenance operations on the steam generator. This survey was augmented by a literature review on the influence of open-quotes hostileclose quotes environment on working conditions. Finally, a specific study was performed in order to quantify the impact of various types of protective suits used in French nuclear installations according to the type of work to be done. All of these factors have been included in a model aiming at quantifying the effectiveness of protection actions, both from dosimetric and economic point of views

ALARA and work management

Energy Technology Data Exchange (ETDEWEB)

Schieber, C. [Centre d`etude sur l`Evaluation de la Protection dans le domaine Nucleaire, Fontenay-aux-Roses (France); Perin, M. [Environmental Radiation Protection and Security Dept., Saint-Denis (France); Saumon, P. [Framatome, Lyon (France)

1995-03-01

At the request of Electricite de France (EDF) and Framatome, the Nuclear Protection Evaluation Centre (CEPN) developed a three-year research project, between 1991 and 1993, to evaluate the impact of various work management factors that can influence occupational exposures in nuclear power plants (NPPs) and to assess the effectiveness of protective actions implemented to reduce them. Three different categories of factors have been delineated: those linked to working conditions (such as ergonomic of work areas and protective suits), those characterizing the operators (qualification, experience level, motivation, etc.). In order to quantify the impact of these factors, a detailed survey was carried out in five French NPPs, focusing on three types of operations: primary valves maintenance, decontamination of reactor cavity, and specialized maintenance operations on the steam generator. This survey was augmented by a literature review on the influence of {open_quotes}hostile{close_quotes} environment on working conditions. Finally, a specific study was performed in order to quantify the impact of various types of protective suits used in French nuclear installations according to the type of work to be done. All of these factors have been included in a model aiming at quantifying the effectiveness of protection actions, both from dosimetric and economic point of views.

Low dose radiation and ALARA: the potential risks to patients and staff from alpha-therapy

International Nuclear Information System (INIS)

Priest, N.D.

2014-01-01

This year a new drug containing radium-223, an alpha-emitting radionuclide, was approved for use by the US Food and Drug Administration for the palliative treatment of advanced prostate cancer metastases. Other drugs containing short-lived alpha-emitters are on clinical trial in Europe. Commonly, these employ a radionuclide attached to an antibody that specifically targets tumor cells to produce a highly localized radio-therapeutic dose to the tumor. However, normal tissues within the body will also be irradiated, albeit sometimes at low dose, and the question arises as to whether this presents a significant additional risk to the patient. Similarly, medical staff that handle these radionuclides could receive intakes of the radionuclides. What is the risk to staff? To assess the risk resulting from small tissue alpha-doses the toxicological, both human and animal, database was re-examined. The results of 20 epidemiological and toxicological studies with alpha-emitting radionuclides were analysed. In all cases a polynomial function provided a better fit to the data than a linear, no thresholds function. Also, in 19 cases a threshold dose below which no cancer is seen was indicated. The position of this threshold varied according to cancer type, but was typically in the range 0.1 to 1.0Gy of tissue dose - with a mean of 0.5Gy. It is concluded that alpha-radiation induced tumorogenesis is a threshold response and that as long as tissue doses are kept below these thresholds no additional cancers would be seen in either patients receiving alpha-therapy or in staff exposed to 'spilt' radionuclide. The presence of thresholds questions the appropriateness of current ALARA practices that are mostly used to drive occupational alpha-radiation exposures to as close to zero as possible. (author)

Low dose radiation and ALARA: the potential risks to patients and staff from alpha-therapy

Energy Technology Data Exchange (ETDEWEB)

Priest, N.D. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

This year a new drug containing radium-223, an alpha-emitting radionuclide, was approved for use by the US Food and Drug Administration for the palliative treatment of advanced prostate cancer metastases. Other drugs containing short-lived alpha-emitters are on clinical trial in Europe. Commonly, these employ a radionuclide attached to an antibody that specifically targets tumor cells to produce a highly localized radio-therapeutic dose to the tumor. However, normal tissues within the body will also be irradiated, albeit sometimes at low dose, and the question arises as to whether this presents a significant additional risk to the patient. Similarly, medical staff that handle these radionuclides could receive intakes of the radionuclides. What is the risk to staff? To assess the risk resulting from small tissue alpha-doses the toxicological, both human and animal, database was re-examined. The results of 20 epidemiological and toxicological studies with alpha-emitting radionuclides were analysed. In all cases a polynomial function provided a better fit to the data than a linear, no thresholds function. Also, in 19 cases a threshold dose below which no cancer is seen was indicated. The position of this threshold varied according to cancer type, but was typically in the range 0.1 to 1.0Gy of tissue dose - with a mean of 0.5Gy. It is concluded that alpha-radiation induced tumorogenesis is a threshold response and that as long as tissue doses are kept below these thresholds no additional cancers would be seen in either patients receiving alpha-therapy or in staff exposed to 'spilt' radionuclide. The presence of thresholds questions the appropriateness of current ALARA practices that are mostly used to drive occupational alpha-radiation exposures to as close to zero as possible. (author)

Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

Energy Technology Data Exchange (ETDEWEB)

Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

1995-02-01

The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

International Nuclear Information System (INIS)

Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

1995-02-01

The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations

High exposure rate hardware ALARA plan

International Nuclear Information System (INIS)

Nellesen, A.L.

1996-10-01

This as low as reasonably achievable review provides a description of the engineering and administrative controls used to manage personnel exposure and to control contamination levels and airborne radioactivity concentrations. HERH waste is hardware found in the N-Fuel Storage Basin, which has a contact dose rate greater than 1 R/hr and used filters. This waste will be collected in the fuel baskets at various locations in the basins

ITER final design report, cost review and safety analysis (FDR) and relevant documents

International Nuclear Information System (INIS)

1999-01-01

This volume contains the fourth major milestone report and documents associated with its acceptance, review and approval. This ITER Final Design Report, Cost Review and Safety Analysis was presented to the ITER Council at its 13th meeting in February 1998 and was approved at its extraordinary meeting on 25 June 1998. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics and schedule and cost estimates are given

A selective review of knowledge-based approaches to database design

Directory of Open Access Journals (Sweden)

Shahrul Azman Noah

1995-01-01

Full Text Available The inclusion of real world knowledge or specialised knowledge has not been addressed by the majority of the systems reviewed. ODA has real world knowledge provided by using a thesaurus-type structure to represent generic models. Only NITDT includes the specialised knowledge in its knowledge base. NITDT classified its knowledge into application specific, domain specific and general knowledge. However the literature does not discuss in detail how this knowledge is applied during the design session. One of the key factors that distinguish computer-based expert systems from human experts is that the latter apply not only their specialised expertise to a problem but also their general knowledge of the world. NITDT is the only system reviewed here that holds any form of internal domain specific knowledge, which can be easily augmented, enriched and updated, as required. This knowledge allows the designer to be an active participant along with the user in the design process and significantly eases the user task. The inclusion of real world knowledge and specialised knowledge is an area that must be further addressed before intelligent tools are able to offer a realistic level of assistance to the human designers.

SRNL Review And Assessment Of WTP UFP-02 Sparger Design And Testing

Energy Technology Data Exchange (ETDEWEB)

Poirier, M. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Duignan, M. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fink, S. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Steimke, J. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-03-24

During aerosol testing conducted by Parsons Constructors and Fabricators, Inc. (PCFI), air sparger plugging was observed in small-scale and medium-scale testing. Because of this observation, personnel identified a concern that the steam spargers in Pretreatment Facility vessel UFP-02 could plug during Waste Treatment and Immobilization Plant (WTP) operation. The U. S. Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) provide consultation on the evaluation of known WTP bubbler, and air and steam sparger issues. The authors used the following approach for this task: reviewed previous test reports (including smallscale testing, medium-scale testing, and Pretreatment Engineering Platform [PEP] testing), met with Bechtel National, Inc. (BNI) personnel to discuss sparger design, reviewed BNI documents supporting the sparger design, discussed sparger experience with Savannah River Site Defense Waste Processing Facility (DWPF) and Sellafield personnel, talked to sparger manufacturers about relevant operating experience and design issues, and reviewed UFP-02 vessel and sparger drawings.

Design Review Report for formal review of safety class features of exhauster system for rotary mode core sampling

International Nuclear Information System (INIS)

JANICEK, G.P.

2000-01-01

Report documenting Formal Design Review conducted on portable exhausters used to support rotary mode core sampling of Hanford underground radioactive waste tanks with focus on Safety Class design features and control requirements for flammable gas environment operation and air discharge permitting compliance

Design Review Report for formal review of safety class features of exhauster system for rotary mode core sampling

Energy Technology Data Exchange (ETDEWEB)

JANICEK, G.P.

2000-06-08

Report documenting Formal Design Review conducted on portable exhausters used to support rotary mode core sampling of Hanford underground radioactive waste tanks with focus on Safety Class design features and control requirements for flammable gas environment operation and air discharge permitting compliance.

Book review. Design for Care: Innovating Healthcare Experience

Directory of Open Access Journals (Sweden)

Manuela Aguirre Ulloa

2014-12-01

Full Text Available Adapted from a review on the same book published by The Design Observer Group on April 4th, 2014. You can access the original publication online at http://designobserver.com/feature/design-for-care/38382/ Peter Jones´ recently published book represents a timely and comprehensive view of the value design brings to healthcare innovation. The book uses an empathic user story that conveys emotions and life to a structure that embraces the different meanings of Design for Care: Spanning from caring at the personal level to large-scale caring systems. The author has a main objective for each of its three main target audiences: Designers, companies and healthcare teams. Firstly, it allows designers to understand healthcare in a holistic and patient-centered way, breaking down specialized silos. Secondly, it shows how to design better care experiences across care continuums. Consequently, for companies serving the healthcare sector, the book presents how to humanize information technology (IT and services and meet the needs of health seekers. Finally, the book aims to inform healthcare teams (clinical practitioners and administrators the value design brings in research, co-creation and implementation of user and organizational experiences. It also proposes that healthcare teams learn and adopt design and systems thinking techniques so their innovation processes can be more participatory, holistic and user-centered.

The Impact of Environmental Design on Teamwork and Communication in Healthcare Facilities: A Systematic Literature Review.

Science.gov (United States)

Gharaveis, Arsalan; Hamilton, D Kirk; Pati, Debajyoti

2018-01-01

The purpose of this systematic review is to investigate the current knowledge about the impact of healthcare facility design on teamwork and communication by exploring the relevant literature. Teamwork and communication are behavioral factors that are impacted by physical design. However, the effects of environmental factors on teamwork and communication have not been investigated extensively in healthcare design literature. There are no published systematic reviews on the current topic. Searches were conducted in PubMed and Google Scholar databases in addition to targeted design journals including Health Environmental Research & Design, Environment and Behavior, Environmental Psychology, and Applied Ergonomics. Inclusion criteria were (a) full-text English language articles related to teamwork and communication and (b) involving any healthcare built environment and space design published in peer-reviewed journals between 1984 and 2017. Studies were extracted using defined inclusion and exclusion criteria. In the first phase, 26 of the 195 articles most relevant to teamwork and 19 studies of the 147 were identified and reviewed to understand the impact of communication in healthcare facilities. The literature regarding the impact of built environment on teamwork and communication were reviewed and explored in detail. Eighteen studies were selected and succinctly summarized as the final product of this review. Environmental design, which involves nurses, support staff, and physicians, is one of the critical factors that promotes the efficiency of teamwork and collaborative communication. Layout design, visibility, and accessibility levels are the most cited aspects of design which can affect the level of communication and teamwork in healthcare facilities.

Investigating Peer Review as a Systemic Pedagogy for Developing the Design Knowledge, Skills, and Dispositions of Novice Instructional Design Students

Science.gov (United States)

Brill, Jennifer M.

2016-01-01

This research investigated peer review as a contemporary instructional pedagogy for fostering the design knowledge, skills, and dispositions of novice Instructional Design and Technology (IDT) professionals. Participants were graduate students enrolled in an introductory instructional design (ID) course. Survey, artifact, and observation data were…

Design and manufacturing challenges of optogenetic neural interfaces: a review

Science.gov (United States)

Goncalves, S. B.; Ribeiro, J. F.; Silva, A. F.; Costa, R. M.; Correia, J. H.

2017-08-01

Optogenetics is a relatively new technology to achieve cell-type specific neuromodulation with millisecond-scale temporal precision. Optogenetic tools are being developed to address neuroscience challenges, and to improve the knowledge about brain networks, with the ultimate aim of catalyzing new treatments for brain disorders and diseases. To reach this ambitious goal the implementation of mature and reliable engineered tools is required. The success of optogenetics relies on optical tools that can deliver light into the neural tissue. Objective/Approach: Here, the design and manufacturing approaches available to the scientific community are reviewed, and current challenges to accomplish appropriate scalable, multimodal and wireless optical devices are discussed. Significance: Overall, this review aims at presenting a helpful guidance to the engineering and design of optical microsystems for optogenetic applications.

Designing and Integrating Purposeful Learning in Game Play: A Systematic Review

Science.gov (United States)

Ke, Fengfeng

2016-01-01

Via a systematic review of the literature on learning games, this article presents a systematic discussion on the design of intrinsic integration of domain-specific learning in game mechanics and game world design. A total of 69 articles ultimately met the inclusion criteria and were coded for the literature synthesis. Exemplary learning games…

N-Basin water removal plan

International Nuclear Information System (INIS)

Nellesen, A.L.

1997-07-01

This ALARA review provides a description of the engineering and administrative controls used to manage personnel exposure, control contamination levels, and airborne radioactivity concentrations, while removing water and stabilizing surfaces in the 105-N Fuel Storage Building

Experience in the review of utility control room design review and safety parameter display system programs

International Nuclear Information System (INIS)

Moore, V.A.

1985-01-01

The Detailed Control Room Design Review (DCRDR) and the Safety Parameter Display System (SPDS) had their origins in the studies and investigations conducted as the result of the TMI-2 accident. The President's Commission (Kemeny Commission) critized NRC for not examining the man-machine interface, over-emphasizing equipment, ignoring human beings, and tolerating outdated technology in control rooms. The Commission's Special Inquiry Group (Rogovin Report) recommended greater application of human factors engineering including better instrumentation displays and improved control room design. The NRC Lessons Learned Task Force concluded that licensees should review and improve control rooms using NRC Human engineering guidelines, and install safety parameter display systems (then called the safety staff vector). The TMI Action Plan Item I.D.1 and I.D.2 were based on these recommendations

Draft audit report, human factors engineering control room design review: Saint Lucie Nuclear Power Plant, Unit No. 2

International Nuclear Information System (INIS)

Peterson, L.R.; Lappa, D.A.; Moore, J.W.

1981-01-01

A human factors engineering preliminary design review of the Saint Lucie Unit 2 control room was performed at the site on August 3 through August 7, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The review team included human factors consultants from BioTechnology, Inc., Falls Church, Virginia, and from Lawrence Livermore National Laboratory (University of California), Livermore, California

Entropy Applications to Water Monitoring Network Design: A Review

Directory of Open Access Journals (Sweden)

Jongho Keum

2017-11-01

Full Text Available Having reliable water monitoring networks is an essential component of water resources and environmental management. A standardized process for the design of water monitoring networks does not exist with the exception of the World Meteorological Organization (WMO general guidelines about the minimum network density. While one of the major challenges in the design of optimal hydrometric networks has been establishing design objectives, information theory has been successfully adopted to network design problems by providing measures of the information content that can be deliverable from a station or a network. This review firstly summarizes the common entropy terms that have been used in water monitoring network designs. Then, this paper deals with the recent applications of the entropy concept for water monitoring network designs, which are categorized into (1 precipitation; (2 streamflow and water level; (3 water quality; and (4 soil moisture and groundwater networks. The integrated design method for multivariate monitoring networks is also covered. Despite several issues, entropy theory has been well suited to water monitoring network design. However, further work is still required to provide design standards and guidelines for operational use.

Radiation dose optimization research: Exposure technique approaches in CR imaging – A literature review

International Nuclear Information System (INIS)

Seeram, Euclid; Davidson, Rob; Bushong, Stewart; Swan, Hans

2013-01-01

The purpose of this paper is to review the literature on exposure technique approaches in Computed Radiography (CR) imaging as a means of radiation dose optimization in CR imaging. Specifically the review assessed three approaches: optimization of kVp; optimization of mAs; and optimization of the Exposure Indicator (EI) in practice. Only papers dating back to 2005 were described in this review. The major themes, patterns, and common findings from the literature reviewed showed that important features are related to radiation dose management strategies for digital radiography include identification of the EI as a dose control mechanism and as a “surrogate for dose management”. In addition the use of the EI has been viewed as an opportunity for dose optimization. Furthermore optimization research has focussed mainly on optimizing the kVp in CR imaging as a means of implementing the ALARA philosophy, and studies have concentrated on mainly chest imaging using different CR systems such as those commercially available from Fuji, Agfa, Kodak, and Konica-Minolta. These studies have produced “conflicting results”. In addition, a common pattern was the use of automatic exposure control (AEC) and the measurement of constant effective dose, and the use of a dose-area product (DAP) meter

The utility perspective on the transportation interface

International Nuclear Information System (INIS)

Bishop, R.W.

1986-01-01

Describing interface between the transportation system and the operating plants, the author thinks there are really three, interrelated dimensions to the interface; the technical; physical interface; the business (i.e. economic) interface; and the institutional interface. A principal mission of the Nuclear Transportation Group is to help assure that these interfaces are smoothly bridged and that the resources of the utility industry are brought to bear to achieve this result. The physical interface is the most readily understood. The analysis must also consider the ALARA (As Low As Reasonably Achievable) radiation exposure evaluation of the waste system design and operation. ALARA evaluations of the waste system design and operation. ALARA evaluations must be done on a systems basis to ensure that the effects of particular designs that may be beneficial in some aspects of the system do not adversely impact nuclear power plant workers or operations. Regardless of one's political persuasion or technical training, the author doesn't think there is any question that spent fuel must be moved, sooner or later, somewhere. It's in the best interests of all that those shipments be made safely, and economically, with the proper attention to doing it right and not needlessly wasting resources, including money

Design of experiments for microencapsulation applications: A review.

Science.gov (United States)

Paulo, Filipa; Santos, Lúcia

2017-08-01

Microencapsulation techniques have been intensively explored by many research sectors such as pharmaceutical and food industries. Microencapsulation allows to protect the active ingredient from the external environment, mask undesired flavours, a possible controlled release of compounds among others. The purpose of this review is to provide a background of design of experiments in microencapsulation research context. Optimization processes are required for an accurate research in these fields and therefore, the right implementation of micro-sized techniques at industrial scale. This article critically reviews the use of the response surface methodologies in pharmaceutical and food microencapsulation research areas. A survey of optimization procedures in the literature, in the last few years is also presented. Copyright © 2017 Elsevier B.V. All rights reserved.

Review: BNL Tokamak graphite blanket design concepts

International Nuclear Information System (INIS)

Fillo, J.A.; Powell, J.R.

1976-01-01

The BNL minimum activity graphite blanket designs are reviewed, and three are discussed in the context of an experimental power reactor (EPR) and commercial power reactor. Basically, the three designs employ a 30 cm or thicker graphite screen. Bremsstrahlung energy is deposited on the graphite surface and re-radiated away as thermal radiation. Fast neutrons are slowed down in the graphite, depositing most of their energy, which is then radiated to a secondary blanket with coolant tubes, as in types A and B, or removed by intermittent direct gas cooling (type C). In types A and B, radiation damage to the coolant tubes in the secondary blanket is reduced by one or two orders of magnitude, while in type C, the blanket is only cooled when the reactor is shut down, so that coolant cannot quench the plasma. (Auth.)

Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 2. Evaluation of seismic designs: a review of seismic design requirements for Nuclear Power Plant Piping

Energy Technology Data Exchange (ETDEWEB)

1985-04-01

This document reports the position and recommendations of the NRC Piping Review Committee, Task Group on Seismic Design. The Task Group considered overlapping conservation in the various steps of seismic design, the effects of using two levels of earthquake as a design criterion, and current industry practices. Issues such as damping values, spectra modification, multiple response spectra methods, nozzle and support design, design margins, inelastic piping response, and the use of snubbers are addressed. Effects of current regulatory requirements for piping design are evaluated, and recommendations for immediate licensing action, changes in existing requirements, and research programs are presented. Additional background information and suggestions given by consultants are also presented.

Transferring Knowledge from Building Operation to Design: A literature review

DEFF Research Database (Denmark)

Rasmussen, Helle Lohmann; Jensen, Per Anker; Gregg, Jay Sterling

. Knowing that the list lacks inputs from cultural and organizational theory, the paper suggests that further research should focus on taking these suggestions to an operational level for the benefit of FM, building clients and design teams. Furthermore, it is found that major concepts that could......As a solution to the previously identified gap between expected and actual building performance, this paper investigates how knowledge can be transferred from operation to design. This is assumed to help bridge the gap and increase the performance of new built facilities. By conducting a systematic...... literature review, it is found, that the theoretical approach in the reviewed articles has a significant impact on the level of how applicable the recommendations are in practice. Furthermore, a list of identified tools to enable knowledge transfer is provided, including POE, PPP and building commissioning...

The Design of High Efficiency Crossflow Hydro Turbines: A Review and Extension

Directory of Open Access Journals (Sweden)

Ram Adhikari

2018-01-01

Full Text Available Efficiency is a critical consideration in the design of hydro turbines. The crossflow turbine is the cheapest and easiest hydro turbine to manufacture and so is commonly used in remote power systems for developing countries. A longstanding problem for practical crossflow turbines is their lower maximum efficiency compared to their more advanced counterparts, such as Pelton and Francis turbines. This paper reviews the experimental and computational studies relevant to the design of high efficiency crossflow turbines. We concentrate on the studies that have contributed to designs with efficiencies in the range of 88–90%. Many recent studies have been conducted on turbines of low maximum efficiency, which we believe is due to misunderstanding of design principles for achieving high efficiencies. We synthesize the key results of experimental and computational fluid dynamics studies to highlight the key fundamental design principles for achieving efficiencies of about 90%, as well as future research and development areas to further improve the maximum efficiency. The main finding of this review is that the total conversion of head into kinetic energy in the nozzle and the matching of nozzle and runner designs are the two main design requirements for the design of high efficiency turbines.

Support for designing waste sorting systems: A mini review.

Science.gov (United States)

Rousta, Kamran; Ordoñez, Isabel; Bolton, Kim; Dahlén, Lisa

2017-11-01

This article presents a mini review of research aimed at understanding material recovery from municipal solid waste. It focuses on two areas, waste sorting behaviour and collection systems, so that research on the link between these areas could be identified and evaluated. The main results presented and the methods used in the articles are categorised and appraised. The mini review reveals that most of the work that offered design guidelines for waste management systems was based on optimising technical aspects only. In contrast, most of the work that focused on user involvement did not consider developing the technical aspects of the system, but was limited to studies of user behaviour. The only clear consensus among the articles that link user involvement with the technical system is that convenient waste collection infrastructure is crucial for supporting source separation. This mini review reveals that even though the connection between sorting behaviour and technical infrastructure has been explored and described in some articles, there is still a gap when using this knowledge to design waste sorting systems. Future research in this field would benefit from being multidisciplinary and from using complementary methods, so that holistic solutions for material recirculation can be identified. It would be beneficial to actively involve users when developing sorting infrastructures, to be sure to provide a waste management system that will be properly used by them.

Conceptual design of an RTG Shipping and Receiving Facility Transportation System

International Nuclear Information System (INIS)

Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

1994-01-01

The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines

Conceptual design of an RTG shipping and receiving facility transportation system

International Nuclear Information System (INIS)

Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

1995-01-01

The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines. copyright 1995 American Institute of Physics

How Games are Designed to Increase Students’ Motivation in Learning Physics? A Literature Review

Science.gov (United States)

Tinedi, V.; Yohandri, Y.; Djamas, D.

2018-04-01

Game is a promising tool to help students in understanding physics concept. It can motivate and provide the opportunities for students to become independent in learning. In order to fulfil these functions, games should be carefully designed. Thus, the objective of this paper is to present how games are designed to increase students’ motivation in learning physics based on several literature reviews. The results showed that there are several ways to increase students’ motivation in learning physics and to achieve that, game dimensions are needed to be considered when designing a game. This literature review may have useful to assist teachers and contribute in improving the design of games.

Final design review report for K Basin Dose Reduction Project Clean and Coat Task

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-02-01

The strategy for reducing radiation dose originating from radionuclides absorbed in the concrete is to raise the pool water level to provide additional shielding. The concrete walls need to be coated to prevent future radionuclide absorption into the walls. This report documents a final design review of equipment to clean and coat basin walls. The review concluded that the design presented was acceptable for release for fabrication

Human-factors engineering control-room design review/audit: Waterford 3 SES Generating Station, Louisiana Power and Light Company

International Nuclear Information System (INIS)

Savage, J.W.

1983-01-01

A human factors engineering design review/audit of the Waterford-3 control room was performed at the site on May 10 through May 13, 1982. The report was prepared on the basis of the HFEB's review of the applicant's Preliminary Human Engineering Discrepancy (PHED) report and the human factors engineering design review performed at the site. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. The review team was assisted by consultants from Lawrence Livermore National Laboratory (University of California), Livermore, California

Report on the Survey of the Design Review of New Reactor Applications. Volume 3: Reactor

International Nuclear Information System (INIS)

Downey, Steven; Monninger, John; Nevalainen, Janne; Lorin, Aurelie; ); Webster, Philip; Joyer, Philippe; Kawamura, Tomonori; Lankin, Mikhail; Kubanyi, Jozef; Haluska, Ladislav; Persic, Andreja; Reierson, Craig; Kang, Kyungmin; Kim, Walter

2016-01-01

At the tenth meeting of the CNRA Working Group on the Regulation of New Reactors (WGRNR) in March 2013, the Working Group agreed to present the responses to the Second Phase, or Design Phase, of the Licensing Process Survey as a multi-volume text. As such, each report will focus on one of the eleven general technical categories covered in the survey. The general technical categories were selected to conform to the topics covered in the International Atomic Energy Agency (IAEA) Safety Guide GS-G-4.1. This document, which is the third report on the results of the Design Phase Survey, focuses on the Reactor. The Reactor category includes the following technical topics: fuel system design, reactor internals and core support, nuclear design and core nuclear performance, thermal and hydraulic design, reactor materials, and functional design of reactivity control system. For each technical topic, the member countries described the information provided by the applicant, the scope and level of detail of the technical review, the technical basis for granting regulatory authorisation, the skill sets required and the level of effort needed to perform the review. Based on a comparison of the information provided by the member countries in response to the survey, the following observations were made: - Although the description of the information provided by the applicant differs in scope and level of detail among the member countries that provided responses, there are similarities in the information that is required. - All of the technical topics covered in the survey are reviewed in some manner by all of the regulatory authorities that provided responses. - Design review strategies most commonly used to confirm that the regulatory requirements have been met include document review and independent verification of calculations, computer codes, or models used to describe the design and performance of the core and the fuel. - It is common to consider operating experience and

ONWI [Office of Nuclear Waste Isolation] 30% design review findings report for Exploratory Shaft Facility, Deaf Smith site

International Nuclear Information System (INIS)

1987-01-01

Based on the performance of a TMP-05 Design Review with integration into the review, via TMP-22, of comments by SRP contractors other than ONWI, the Design Review Board has developed conclusions and recommendations with respect to the 30% design effort submitted by PB/PB-KBB for interim design review. A number of comments were submitted on the design basis criteria and requirements furnished as guidance to PB/PB-KBB. These comments are forwarded to SRPO for disposition and resolution. Additionally, comments whose resolution by PB/PB-KBB require input from other SRP contractors are included. All comments forwarded to SRPO are compiled and subdivided by appropriate category in Section 11.0 of this Findings Report

Review of updated design of SPWR with PSA methodology

International Nuclear Information System (INIS)

Oikawa, Tetsukuni; Muramatsu, Ken

1995-01-01

This paper presents the procedures and results of a PSA (Probabilistic Safety Assessment) of the SPWR (System-Integrated PWR), which is being developed at the Japan Atomic Energy Research Institute (JAERI) as a medium sized innovative passive safe reactor, to assist in the design improvement of the SPWR at the basic or conceptual design phase by reviewing the design and identifying the design vulnerability. The first phase PSA, which was carried out in 1991, was a scoping analysis in order to understand overall plant characteristics and to search for general design weakness. After discussing the results of the first phase PSA, the SPWR designer group changed some designs of the SPWR. The second phase PSA of the SPWR was performed for the modified design in order to identify the design vulnerability as well as to grasp its overall safety level. Special items of these PSAs are as follows: (1) systematic identification of initiating events related to newly designed systems by the failure mode effect analysis (FMEA), (2) delineation of accident sequences for the internal initiating events using accident progression flow charts which is cost effective for conceptual design phase, (3) quantification of event trees based on many engineering judgement, and (4) lots of sensitivity analyses to examine applicability of data assignment. Qualitative and quantitative results of PSA provided very useful information for decision makings of design improvement and recommendations for further consideration in the process of detailed design. (author)

Conceptual design review report for K Basin Dose Reduction Project clean and coat task

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-01-01

The strategy for reducing radiation dose originating from radionuclides absorbed in the concrete is to raise the pool water level to provide additional shielding. The concrete walls need to be coated to prevent future radionuclide absorption into the walls. This report documents a conceptual design review of equipment to clean and coat basin walls. The review concluded that the proposed concepts were and acceptable basis for proceeding with detailed final design

A Review of Design Optimization Methods for Electrical Machines

Directory of Open Access Journals (Sweden)

Gang Lei

2017-11-01

Full Text Available Electrical machines are the hearts of many appliances, industrial equipment and systems. In the context of global sustainability, they must fulfill various requirements, not only physically and technologically but also environmentally. Therefore, their design optimization process becomes more and more complex as more engineering disciplines/domains and constraints are involved, such as electromagnetics, structural mechanics and heat transfer. This paper aims to present a review of the design optimization methods for electrical machines, including design analysis methods and models, optimization models, algorithms and methods/strategies. Several efficient optimization methods/strategies are highlighted with comments, including surrogate-model based and multi-level optimization methods. In addition, two promising and challenging topics in both academic and industrial communities are discussed, and two novel optimization methods are introduced for advanced design optimization of electrical machines. First, a system-level design optimization method is introduced for the development of advanced electric drive systems. Second, a robust design optimization method based on the design for six-sigma technique is introduced for high-quality manufacturing of electrical machines in production. Meanwhile, a proposal is presented for the development of a robust design optimization service based on industrial big data and cloud computing services. Finally, five future directions are proposed, including smart design optimization method for future intelligent design and production of electrical machines.

Characterization of workplaces in interventional radiology using active dosemeters ALARA OD

International Nuclear Information System (INIS)

Prlic, I.; Milkovic-Kraus, S.; Mestrovic, T.; Suric-Mihic, M.; Vrtar, M.

2005-01-01

Full text: Because of progressive development and extended use of interventional radiology procedures it is highly recommended that all individuals involved in the process should be aware of the potential for both stochastic and deterministic effects due to occupational exposure. Interventional radiology procedures are essentially therapeutic and are performed by various medical specialists, not only by properly educated radiologists. As the procedures are performed in such a manner that certain number of medical staff are always needed near the patient, near the x- ray unit, ensuring 'safe' working environment in such radiation x-ray field geometry is a new challenge to regular radiation protection. In this work we are not primary concerned in relatively high doses delivered to patients undergoing interventional procedures. The patient is rather regarded as a secondary radiation source which emits scattered x-rays. The working staff, moving in mixed, primary and scattered x-ray field, is expected to be exposed to higher occupational doses due to combination of extended fluoroscopy times, elevated fluoroscopy currents and larger amount of radiographic images required. The protection of both patients and staff is to be upgraded. As passive dosemetes will give us clear knowledge only about the monthly integrated occupational dose, a reasonable doubt exists about the frequency and duration, of receiving the dose. Measuring dose rate is not a part of regular passive dosemeters monitoring systems. This is why we have developed active - electronic dosemeter device which provides us with additional dosimetry data about the frequency and duration of professional exposure burden. Digital dosemeter ALARA OD will record and integrate any occupational dose including the normal radiation background in the working area. It will record the time and duration of any fluoroscopic exposure done. This gives us the data about the dose rate of occupational radiation and frequency of

RF power harvesting: a review on designing methodologies and applications

Science.gov (United States)

Tran, Le-Giang; Cha, Hyouk-Kyu; Park, Woo-Tae

2017-12-01

Wireless power transmission was conceptualized nearly a century ago. Certain achievements made to date have made power harvesting a reality, capable of providing alternative sources of energy. This review provides a summ ary of radio frequency (RF) power harvesting technologies in order to serve as a guide for the design of RF energy harvesting units. Since energy harvesting circuits are designed to operate with relatively small voltages and currents, they rely on state-of-the-art electrical technology for obtaining high efficiency. Thus, comprehensive analysis and discussions of various designs and their tradeoffs are included. Finally, recent applications of RF power harvesting are outlined.

Optimizing Mass Spectrometry Analyses: A Tailored Review on the Utility of Design of Experiments.

Science.gov (United States)

Hecht, Elizabeth S; Oberg, Ann L; Muddiman, David C

2016-05-01

Mass spectrometry (MS) has emerged as a tool that can analyze nearly all classes of molecules, with its scope rapidly expanding in the areas of post-translational modifications, MS instrumentation, and many others. Yet integration of novel analyte preparatory and purification methods with existing or novel mass spectrometers can introduce new challenges for MS sensitivity. The mechanisms that govern detection by MS are particularly complex and interdependent, including ionization efficiency, ion suppression, and transmission. Performance of both off-line and MS methods can be optimized separately or, when appropriate, simultaneously through statistical designs, broadly referred to as "design of experiments" (DOE). The following review provides a tutorial-like guide into the selection of DOE for MS experiments, the practices for modeling and optimization of response variables, and the available software tools that support DOE implementation in any laboratory. This review comes 3 years after the latest DOE review (Hibbert DB, 2012), which provided a comprehensive overview on the types of designs available and their statistical construction. Since that time, new classes of DOE, such as the definitive screening design, have emerged and new calls have been made for mass spectrometrists to adopt the practice. Rather than exhaustively cover all possible designs, we have highlighted the three most practical DOE classes available to mass spectrometrists. This review further differentiates itself by providing expert recommendations for experimental setup and defining DOE entirely in the context of three case-studies that highlight the utility of different designs to achieve different goals. A step-by-step tutorial is also provided.

ORNL implementation of new health and safety requirements (DOE Order 5480.11)

International Nuclear Information System (INIS)

Abercrombie, J.S.

1988-01-01

New mandates in radiological protection outlined in DOE Order 5480. 11, include changes in the methodology for determining total radiation dose, ALARA program accountability, monitoring requirements, and standards for public entrance into controlled areas. The new order places distinct requirements concerning training at all DOE facilities. Radiation protection training requirements are addressed, including the effective communication of operations changes to all employees. This paper details the endeavors underway at ORNL in designing, developing, and delivering the training required by the new mandates. Strategies taken to reach the intended goals are explained. Efforts involve the design and implementation of the above mentioned radiation protection programs, a job-specific ALARA instructional package, and a Risk-Based Philosophy program matched to operational changes. 4 refs., 5 tabs

Yucca Mountain Project: ESF Title I design control process review report

International Nuclear Information System (INIS)

1989-01-01

The Exploratory Shaft Facility (ESF) Title 1 Design Control Process Review was initiated in response to direction from the Office of Civilian Radioactive Waste Management (OCRWM) (letter: Kale to Gertz, NRC Concerns on Title 1 Design Control Process, November 17, 1988). The direction was to identify the existing documentation that described ''hor-ellipsis the design control process and the quality assurance that governed hor-ellipsis'' (a) the development of the requirements documents for the ESF design, (b) the various interfaces between activities, (c) analyses and definitions leading to additional requirements in the System Design Requirements Documents and, (d) completion of Title 1 Design. This report provides historical information for general use in determining the extent of the quality assurance program in existence during the ESF Title 1 Design

Virtual radiation fields for ALARA determination

International Nuclear Information System (INIS)

Knight, T.W.

1995-01-01

As computing power has increased, so too has the ability to model and simulate complex systems and processes. In addition, virtual reality technology has made it possible to visualize and understand many complex scientific and engineering problems. For this reason, a virtual dosimetry program called Virtual Radiation Fields (VRF) is developed to model radiation dose rate and cumulative dose to a receptor operating in a virtual radiation environment. With the design and testing of many facilities and products taking place in the virtual world, this program facilitates the concurrent consideration of radiological concerns during the design process. Three-dimensional (3D) graphical presentation of the radiation environment is made possible through the use of IGRIP, a graphical modeling program developed by Deneb Robotics, Inc. The VRF simulation program was designed to model and display a virtual dosimeter. As a demonstration of the program's capability, the Hanford tank, C-106, was modeled to predict radiation doses to robotic equipment used to remove radioactive waste from the tank. To validate VRF dose predictions, comparison was made with reported values for tank C-106, which showed agreement to within 0.5%. Graphical information is presented regarding the 3D dose rate variation inside the tank. Cumulative dose predictions were made for the cleanup operations of tank C-106. A four-dimensional dose rate map generated by VRF was used to model the dose rate not only in 3D space but also as a function of the amount of waste remaining in the tank. This allowed VRF to predict dose rate at any stage in the waste removal process for an accurate simulation of the radiological conditions throughout the tank cleanup procedure

Personalization in Game Design for Healthcare: a Literature Review on its Definitions and Effects

Directory of Open Access Journals (Sweden)

Marierose van Dooren

2016-12-01

Full Text Available Personalization, the involvement of stakeholders in the design process, is often applied in serious game design for health. It is expected to enhance the alignment of a game to the preferences and capacities of the end-user, thereby increasing the end-user’s motivation to interact with the game, which finally might enhance the aimed-for health effects of the game. However, the nature and effect of personalization have never been systematically studied, making assumptions regarding personalization ungrounded. In this literature review, we firstly provide a proposal of our Personalized Design Process-model, where personalization is defined as stakeholder involvement in the Problem Definition-, Product Design- and/or Tailoring Phase. Secondly, we conducted a systematic literature review on this model, focusing on health and its effects. In this review, 62 of the 2579 found studies were included. Analysis showed that a minority of the studies were of methodologically higher quality and some of these tested the health effect by contrasting tailored versus non-tailored games. Most studies involved stakeholders in the Tailoring Design Phase. Therefore, we conclude that involving stakeholders in the Tailoring Phase is valuable. However, to know if personalization is effective in the Product Design- and the Problem Definition Phase, more studies are needed.

Design review report for the Hanford K East and K West Basins MCO loading system

International Nuclear Information System (INIS)

Brisbin, S.A.

1997-01-01

This design report presents the final design of the MCO Loading System. The report includes final design drawings, a system description, failure modes and recovery plans, a system operational description, and stress analysis. Design comments from the final design review have been incorporated

EC6 design features and pre-project licensing review

Energy Technology Data Exchange (ETDEWEB)

Yu, S.; Lee, A.G.; Dinh, N.B.; Soulard, M. [CANDU Energy Inc., Mississauga, Ontario, (Canada)

2013-07-01

The Enhanced CANDU 6 (EC6) is the new Generation III CANDU reactor design that meets the most up to date Canadian regulatory requirements and customer expectations. Candu Energy Inc. is finalizing development of the EC6 which incorporates the CANDU 6's well-proven features, and adds enhancements that strengthened reactor safety margin and improved operability. The EC6 builds on the proven high performance design and the defence-in-depth features of CANDU 6 units, and has incorporated extensive operational feedback including lessons learned from Fukushima. This paper will provide status of the engineering program including progress on the pre-licensing review of the EC6 design by the Canadian Regulator, CNSC, and will also highlight the design and safety enhancements incorporated in the EC6 product. Safety enhancements to meet safety goals and to improve robustness of systems to respond to design basis accidents and beyond design basis accidents include: new severe accident recovery and heat removal system; improved emergency heat removal system; faster shutoff rods with improved safety margins; mechanical guaranteed shutdown rods; daily load cycling capability; robust containment with containment filter venting system; and improved backed-up electrical supply and cooling services. (author)

Optimization of the workers radiation protection in the electro nuclear, industrial and medical fields; Optimisation de la radioprotection des travailleurs dans les domaines electronucleaire, industriel et medical

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This conference is devoted to the radiation protection and the best way to optimize it. It reviews each area of the nuclear industry, and explores also the medical sector. Dosimetry, ALARA principle and new regulation are important points of this meeting. (N.C.)

Optimization of the workers radiation protection in the electro nuclear, industrial and medical fields

International Nuclear Information System (INIS)

1998-01-01

This conference is devoted to the radiation protection and the best way to optimize it. It reviews each area of the nuclear industry, and explores also the medical sector. Dosimetry, ALARA principle and new regulation are important points of this meeting. (N.C.)

Virtual radiation fields for ALARA determination

Energy Technology Data Exchange (ETDEWEB)

Knight, T.W.

1995-12-31

As computing power has increased, so too has the ability to model and simulate complex systems and processes. In addition, virtual reality technology has made it possible to visualize and understand many complex scientific and engineering problems. For this reason, a virtual dosimetry program called Virtual Radiation Fields (VRF) is developed to model radiation dose rate and cumulative dose to a receptor operating in a virtual radiation environment. With the design and testing of many facilities and products taking place in the virtual world, this program facilitates the concurrent consideration of radiological concerns during the design process. Three-dimensional (3D) graphical presentation of the radiation environment is made possible through the use of IGRIP, a graphical modeling program developed by Deneb Robotics, Inc. The VRF simulation program was designed to model and display a virtual dosimeter. As a demonstration of the program`s capability, the Hanford tank, C-106, was modeled to predict radiation doses to robotic equipment used to remove radioactive waste from the tank. To validate VRF dose predictions, comparison was made with reported values for tank C-106, which showed agreement to within 0.5%. Graphical information is presented regarding the 3D dose rate variation inside the tank. Cumulative dose predictions were made for the cleanup operations of tank C-106. A four-dimensional dose rate map generated by VRF was used to model the dose rate not only in 3D space but also as a function of the amount of waste remaining in the tank. This allowed VRF to predict dose rate at any stage in the waste removal process for an accurate simulation of the radiological conditions throughout the tank cleanup procedure.

A Review Of Design And Control Of Automated Guided Vehicle Systems

OpenAIRE

Le-Anh, Tuan; Koster, René

2004-01-01

textabstractThis paper presents a review on design and control of automated guided vehicle systems. We address most key related issues including guide-path design, estimating the number of vehicles, vehicle scheduling, idle-vehicle positioning, battery management, vehicle routing, and conflict resolution. We discuss and classify important models and results from key publications in literature on automated guided vehicle systems, including often-neglected areas, such as idle-vehicle positionin...

A Year of Progress: NASA's Space Launch System Approaches Critical Design Review

Science.gov (United States)

Askins, Bruce; Robinson, Kimberly

2015-01-01

NASA's Space Launch System (SLS) made significant progress on the manufacturing floor and on the test stand in 2014 and positioned itself for a successful Critical Design Review in mid-2015. SLS, the world's only exploration-class heavy lift rocket, has the capability to dramatically increase the mass and volume of human and robotic exploration. Additionally, it will decrease overall mission risk, increase safety, and simplify ground and mission operations - all significant considerations for crewed missions and unique high-value national payloads. Development now is focused on configuration with 70 metric tons (t) of payload to low Earth orbit (LEO), more than double the payload of the retired Space Shuttle program or current operational vehicles. This "Block 1" design will launch NASA's Orion Multi-Purpose Crew Vehicle (MPCV) on an uncrewed flight beyond the Moon and back and the first crewed flight around the Moon. The current design has a direct evolutionary path to a vehicle with a 130t lift capability that offers even more flexibility to reduce planetary trip times, simplify payload design cycles, and provide new capabilities such as planetary sample returns. Every major element of SLS has successfully completed its Critical Design Review and now has hardware in production or testing. In fact, the SLS MPCV-to-Stage-Adapter (MSA) flew successfully on the Exploration Flight Test (EFT) 1 launch of a Delta IV and Orion spacecraft in December 2014. The SLS Program is currently working toward vehicle Critical Design Review in mid-2015. This paper will discuss these and other technical and programmatic successes and challenges over the past year and provide a preview of work ahead before the first flight of this new capability.

Utilizing 3D-visualization to apply compulsory ALARA principles in nuclear power plant design and day-to-day operation

Energy Technology Data Exchange (ETDEWEB)