WorldWideScience

Sample records for alara design review

  1. Fuel transfer system ALARA design review - Project A.15

    International Nuclear Information System (INIS)

    KUEBERTH, L.R.

    2001-01-01

    One mission of the Spent Nuclear Fuel (SNF) Project is to move the SNF from the K Basins in the Hanford 100K Area to an interim dry storage at the Canister Storage Building (CSB) in the Hanford 200 East Area. The Fuel Transfer System (FTS) is a subproject that will move the SNF from the 105K East (KE) Facility to the 105K West (KW) Facility. The SNF will be treated for shipment to the Cold Vacuum Drying (CVD) facility at the KW Basin. The SNF canisters will be loaded underwater into a Shielded Transfer Cask (STC) in the KE Basin. The fully loaded STC will be brought out of the water and placed into a Cask Transfer Overpack (CTO) by the STC Straddle Carrier. As the STC is removed from the water, it will be washed down with demineralized water by an manual rinse system. The CTO with the STC inside will be placed on a transport trailer and transferred to the KW Basin as an intra-facility transfer. The CTO will be unloaded from the shipping trailer at the KW Basin and the STC will be removed from the CTO. The STC will then be lowered into the KW Basin water and the fuel will be removed. The SNF will then be processed for shipment to the CVD. As soon as all of the fuel has been removed from the STC, the cask will be removed from the KW Basin water and placed into the CTO. The CTO will again be placed on the trailer for transport back to the KE Basin where the entire cycle will be repeated approximately 400 times. This document records the As Low As Reasonably Achievable (ALARA) findings and design recommendations/requirements by the SNF Project noted during the Final Design Review of the STC, CTO, STC Transfer System, Annexes and Roadways for support of FTS. This document is structured so that all statements that include the word ''shall'' represent design features that have been or will be implemented within the project scope. Statements that include the words ''should'' or ''recommend'' represent ALARA design features to be evaluated for future implementation

  2. ALARA Design Review for the Resumption of the Plutonium Finishing Plant (PFP) Cementation Process Project Activities

    CERN Document Server

    Dayley, L

    2000-01-01

    The requirements for the performance of radiological design reviews are codified in 10CFR835, Occupational Radiation Protection. The basic requirements for the performance of ALARA design reviews are presented in the Hanford Site Radiological Control Manual (HSRCM). The HSRCM has established trigger levels requiring radiological reviews of non-routine or complex work activities. These requirements are implemented in site procedures HNF-PRO-1622 and 1623. HNF-PRO-1622 Radiological Design Review Process requires that ''radiological design reviews [be performed] of new facilities and equipment and modifications of existing facilities and equipment''. In addition, HNF-PRO-1623 Radiological Work Planning Process requires a formal ALARA Review for planned activities that are estimated to exceed 1 person-rem total Dose Equivalent (DE). The purpose of this review is to validate that the original design for the PFP Cementation Process ensures that the principles of ALARA (As Low As Reasonably Achievable) were included...

  3. Catawba nuclear station preoperational ALARA review

    International Nuclear Information System (INIS)

    Deal, W.P.

    1985-01-01

    This paper describes the particular emphasis placed on preoperational as los as reasonably achievable (ALARA) considerations at Duke Power's Catawba Nuclear Station. A strong station commitment to the ALARA philosophy, and review of existing capabilities, led to development of an aggressive two-part ALARA program. Capabilities consisted of sufficient numbers of available personnel, lengthy lead time during construction, a very detailed plastic model, and a sister plant of similar design. The program, as developed, consisted of a preoperational program, which looked at design and construction aspects of ALARA, and the operational program, dealing with the ALARA committee and operational problems. MAnagement's philosophy of holding everyone responsible for ALARA provided the motivation to organize the preoperational program to use that resource. The Health Physics group accepted responsibility for development, coordination, and reviewer training. The problem provided a base to build on as station personnel gained experience in their own crafts and radiation protection in general

  4. Preliminary ALARA design concept for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs.

  5. Preliminary ALARA design concept for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs.

  6. Preliminary ALARA design concept for SMART

    International Nuclear Information System (INIS)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs

  7. Elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities

    International Nuclear Information System (INIS)

    Lefaure, C.; Croft, J.R.

    1991-01-01

    This article briefly reviews the three fundamental elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities. These are the need for commitment of all parties involved, the need for specific ALARA organizational structures and the systematic use of ALARA tools. (UK)

  8. ALARA Review of 233-S Process Hood D and D and Related Activities

    International Nuclear Information System (INIS)

    Landsman, S.D.

    1999-01-01

    This document is an as low as reasonably achievable (ALARA) review of design packages for planned work at the 233-S Facility. The ALARA review was initiated in accordance with the Bechtel Hanford, Inc. (BHI) Integrated Environmental, Safety, and Health Management System (ISMS) workflow process

  9. ALARA Review of the SHAARS Operation

    International Nuclear Information System (INIS)

    Kekana, R.M.T.

    2010-01-01

    The SHARS mobile hot cell was designed and manufactured by Necsa intended to address the problem of disused Spent High Activity Radioactive Sources (SHARS) from teletherapy units, gamma irradiators and brachytherapy units. This unit is to be used in countries with no remote infrastructure to handle SHARS. The hot cell was designed for a 3.7E+13Bq (1000Ci) activity although it was demonstrated that it can handle even more than 7.4E+13Bq (2000Ci). The unit has a biological shield which consists of river sand sandwiched between metal plates and a viewing window filled with 50% zinc bromide solution. The unit was designed to provide sufficient shielding to ensure that doses are kept ALARA (As low As Reasonably Achieved). This paper compares the modelled dose rates with the actual measured doses during operations conducted in Sudan, Tanzania and Uruguay. It also presents the key lessons learned in the application of the ALARA principle during the SHARS missions. The new working practices and additional methods are proposed in order to reduce doses in accordance with the ALARA principle. (author)

  10. 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

  11. An operating nuclear utility's experience with the ALARA design of a new nuclear unit

    International Nuclear Information System (INIS)

    Rodgers, R.C.

    1985-01-01

    This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

  12. ALARA development in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, M.A.M. [Instituto Nacional de Investigaciones Nucleares, Col Lomas de Barrilaco (Mexico)

    1995-03-01

    Even though the ALARA philosophy was formally implemented in the early 1980`s, to some extent, ALARA considerations already had been incorporated into the design of most commercial equipment and facilities based on experience and engineering development. In Mexico, the design of medical and industrial facilities were based on international recommendations containing those considerations. With the construction of Laguna Verde Nuclear Power Station, formal ALARA groups were created to review some parts of its design, and to prepare the ALARA Program and related procedures necessary for its commercial operation. This paper begins with a brief historical description of ALARA development in Mexico, and then goes on to discuss our regulatory frame in Radiation Protection, some aspects of the ALARA Program, efforts in controlling and reducing of sources of radiation, and finally, future perspectives in the ALARA field.

  13. 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

  14. Designing plants for ALARA-revelation or evolution

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The author traces the Duke Nuclear program from the late 1960s to today. He then looks at the future. The primary goal, he says, should be to continue to reduce individual exposure in order to reduce total station, industry exposure. In order to accomplish this goal in the design process, he recommends continued training of design personnel to reinforce the ALARA concepts and to provide new industry techniques and actual examples

  15. 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

  16. ALARA Review of the Spallation Neutron Source Accumulator Ring and Transfer Lines

    Energy Technology Data Exchange (ETDEWEB)

    Haire, M.J.

    2003-06-30

    The Spallation Neutron Source (SNS) is designed to meet the growing need for new tools that will deepen our understanding in materials science, life science, chemistry, fundamental and nuclear physics, earth and environmental sciences, and engineering sciences. The SNS is an accelerator-based neutron-scattering facility that when operational will produce an average beam power of 2 MW at a repetition rate of 60 Hz. The accelerator complex consists of the front-end systems, which will include an ion source; a 1-GeV full-energy linear accelerator; a single accumulator ring and its transfer lines; and a liquid mercury target. This report documents an as-low-as-reasonably-achievable (ALARA) review of the accumulator ring and transfer lines at their early design stage. An ALARA working group was formed and conducted a review of the SNS ring and transfer lines at the {approx}25% complete design stage to help ensure that ALARA principles are being incorporated into the design. The radiological aspects of the SNS design criteria were reviewed against regulatory requirements and ALARA principles. Proposed features and measures were then reviewed against the SNS design criteria. As part of the overall review, the working group reviewed the design manual; design drawings and process and instrumentation diagrams; the environment, safety, and health manual; and other related reports and literature. The group also talked with SNS design engineers to obtain explanations of pertinent subject matter. The ALARA group found that ALARA principles are indeed being incorporated into the early design stage. Radiation fields have been characterized, and shielding calculations have been performed. Radiological issues are being adequately addressed with regard to equipment selection, access control, confinement structure and ventilation, and contamination control. Radiation monitoring instrumentation for worker and environment protection are also being considered--a good practice at this

  17. ALARA Review for the Sediment Relocation and Removal from the 105-N Fuel Storage Basin

    International Nuclear Information System (INIS)

    Demers, J.W.

    1998-01-01

    This as low as reasonable achievable (ALARA) review revision provides a description of the engineering and administrative controls used to manage personnel exposure, control contamination levels, and airborne radioactivity concentrations during sediment relocation and removal in the 105-N Fuel Storage Basin. This document updates and supercedes the ALARA review of the sediment-related activities contained in 100-N Basin Stabilization Project As Low As Reasonably Achievable Plan (BHI 1995)

  18. 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

  19. BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

    International Nuclear Information System (INIS)

    Dionne, B.J.; Masciulli, S.; 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 of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents 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 Radiological Assessment and Design System (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 analyses, (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 rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

  20. Alara in industry

    International Nuclear Information System (INIS)

    Croft, J.R.

    1989-01-01

    This paper reviews how the general frameworks of the ALARA procedures, ALARA Audits and Predictive ALARA Plans can be used in the non-nuclear power sector to give practical effect to the concept of optimization. The development of the use of ALARA Audits as an integral part of a Radiation Protection Adviser service and our experience of this structured approach is described. Particular attention is drawn to the use of site specific reference levels to trigger graded levels of response to increasing doses. Also several examples of the use of Cost Benefit Analysis within the ALARA Procedure are briefly described

  1. ALARA Review for the Deactivation of the 107-N Pump Well

    International Nuclear Information System (INIS)

    Edwards, T.A.

    1998-01-01

    This as low as reasonably achievable (ALARA) review provides a description of the engineering and administrative controls used during the completion of deactivation work at the 107-N Building. This ALARA assessment focuses on the 107-N Building pump well. The level of contamination found in the pump well has been estimated to be approximately 830 mRad/hr beta and 680,000 disintegrations per minute (dpm) alpha per large area wipe. As part of the characterization of the water and sediment, samples were taken to determine the isotopic distribution

  2. 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

  3. 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)

  4. 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)

  5. What is ALARA

    International Nuclear Information System (INIS)

    Auxier, J.A.; Dickson, H.W.

    1981-01-01

    The as-low-as-reasonably-achievable (ALARA) philosophy as it applies to personnel radiation exposure has been with us for a long time. The essential tenets of this philosophy surfaced quite early in the history of the Manhattan Project. Although the terminology has suffered through various translations and the application has seen many organizations and agencies come and go, the principles remain as valid today as ever. It is regretable that some regulatory agencies claim ALARA as their newfound miracle drug and that application according to their prescriptions will result in endless rounds of cyclical improvement in radiation protection practices. Others have taken advantage of the popularity of ALARA and have bastardized the philosophy to mean whatever is expedient for their purposes. In this paper, we review briefly the history of ALARA and what it seemingly means to different interest groups and offer a balanced viewpoint that health physicists should adopt

  6. ALARA for nuclear power plant operation

    International Nuclear Information System (INIS)

    Knapp, P.J.

    1979-01-01

    The concept of maintaining radiation exposures as low as reasonably achievable (ALARA) is outlined in connection with nuclear power plant operations. The basis of the concept is reviewed and a specific example of ALARA action is presented. (author)

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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)

  14. 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

  15. 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)

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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)

  1. 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)

  2. 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)

  3. 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

  4. 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.

  5. 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.

  6. ALARA radiation considerations for the AP600 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lau, F.L. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1995-03-01

    The radiation design of the AP600 reactor plant is based on an average annual occupational radiation exposure (ORE) of 100 man-rem. As a design goal we have established a lower value of 70 man-rem per year. And, with our current design process, we expect to achieve annual exposures which are well below this goal. To accomplish our goal we have established a process that provides criteria, guidelines and customer involvement to achieve the desired result. The criteria and guidelines provide the shield designer, as well as the systems and plant layout designers with information that will lead to an integrated plant design that minimizes personnel exposure and yet is not burdened with complicated shielding or unnecessary component access limitations. Customer involvement is provided in the form of utility input, design reviews and information exchange. Cooperative programs with utilities in the development of specific systems or processes also provides for an ALARA design. The results are features which include ALARA radiation considerations as an integral part of the plant design and a lower plant ORE. It is anticipated that a further reduction in plant personnel exposures will result through good radiological practices by the plant operators. The information in place to support and direct the plant designers includes the Utility Requirements Document (URD), Federal Regulations, ALARA guidelines, radiation design information and radiation and shielding design criteria. This information, along with the utility input, design reviews and information feedback, will contribute to the reduction of plant radiation exposure levels such that they will be less than the stated goals.

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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)

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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)

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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.

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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.

  16. Utilizing 3D-visualization to apply compulsory ALARA principles in nuclear power plant design and day-to-day operation

    Energy Technology Data Exchange (ETDEWEB)

    Sanders, R. L.; Lake, J. E. [Oak Ridge National Laboratory, Computational Sciences and Engineering Div., Mail Stop 6085, One Bethel Valley Road, Oak Ridge, TN 37831 (United States)

    2006-07-01

    The development of an advanced visualization and simulation tool to support both design as well as day-to-day operation is presented. This tool exploits cutting edge computer graphics, physics-based effects modeling, virtual reality, and gaming technologies to establish a system that can eventually be used for the administrative planning and training of plant operators and design engineers. (authors)

  17. Utilizing 3D-visualization to apply compulsory ALARA principles in nuclear power plant design and day-to-day operation

    International Nuclear Information System (INIS)

    Sanders, R. L.; Lake, J. E.

    2006-01-01

    The development of an advanced visualization and simulation tool to support both design as well as day-to-day operation is presented. This tool exploits cutting edge computer graphics, physics-based effects modeling, virtual reality, and gaming technologies to establish a system that can eventually be used for the administrative planning and training of plant operators and design engineers. (authors)

  18. 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)

  19. 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.

  20. 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)

  1. 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)

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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.)

  8. 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

  9. 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.

  10. 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).

  11. 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)

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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)

  17. 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

  18. 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.)

  19. 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

  20. 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.

  1. Design Review Improvement Recommendations

    Science.gov (United States)

    2015-06-18

    Worcester, Boeing Anne Ramsey, Harris Corporation Ronald H. Mandel, Lockheed Martin Mark King, Micropac Industries Melanie Berg, NASA Cindy...Peters, Raytheon Donna Potter , SSL ii Executive Summary The aerospace industry continues to experience design escapes that significantly impact

  2. 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

  3. 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.

  4. 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

  5. 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...

  6. 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)

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.)

  18. 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.

  19. 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

  20. 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

  1. 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.

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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

  11. 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)

  12. 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.

  13. 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

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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.

  8. ALARA organization in nuclear power stations

    International Nuclear Information System (INIS)

    Dollo, R.

    1997-01-01

    EDF's nuclear power stations were built with provisions being made, as from the design stage, to limit radiation sources and the results observed over the first ten years (annual collective dose and dose per unit of less than 2 man.Sv) were considered to be very good. However, these results began to deteriorate from 1988 onwards. At the same time, considerable progress was being made by other generators of electricity, who were achieving results which were better than those achieved by our later units. Furthermore, radiological protection standards are being revised and personal dose limits will soon be lowered. (authors)

  9. 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

  10. 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

  11. 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

  12. Experimental Design: Review and Comment.

    Science.gov (United States)

    1984-02-01

    creativity. Innovative modifications and extensions of classical experimental designs were developed and many useful articles were published in a short...Pjrazolone Industrielle ," Bulletin de la Soci~t6 Chimique de France, 11-12, 1171-1174. LI, K. C. (1983), "Minimaxity for Randomized Designs: Some

  13. 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

  14. 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

  15. A review of model designs

    NARCIS (Netherlands)

    Verdonschot, P.F.M.; Nijboer, R.C.

    2002-01-01

    The PAEQANN project aims to review current ecological theories which can help identify suited models that predict community structure in aquatic ecosystems, to select and discuss appropriate models, depending on the type of target community (i.e. empirical vs. simulation models) and to examine how

  16. 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)

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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.)

  5. 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

  6. 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)

  7. 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

  8. 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)

  9. 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

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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

  1. 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)

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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.

  10. 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

  11. 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)

  12. 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

  13. 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.)

  14. 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)

  15. 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)

  16. 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

  17. 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.

  18. Preliminary design review: Brayton Isotope Power System

    International Nuclear Information System (INIS)

    The design aspects covered include flight system design, design criteria/margins/reliability, GDS design, system analysis, materials, system assembly procedure, and government furnished equipment-BTPS

  19. 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.)

  20. 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

  1. 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

  2. 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

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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...

  9. 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...

  10. 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

  11. 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...

  12. WWC Study Review Guide: Group Design Studies

    Science.gov (United States)

    What Works Clearinghouse, 2018

    2018-01-01

    Underlying all What Works Clearinghouse (WWC) products are WWC Study Review Guides, which are intended for use by WWC certified reviewers to assess studies against the WWC evidence standards. As part of an ongoing effort to increase transparency, promote collaboration, and encourage widespread use of the WWC standards, the Institute of Education…

  13. LHCb RICH1 Engineering Design Review Report

    CERN Document Server

    Brook, N; Metlica, F; Muir, A; Phillips, A; Buckley, A; Gibson, V; Harrison, K; Jones, C R; Katvars, S G; Lazzeroni, C; Storey, J; Ward, CP; Wotton, S; Alemi, M; Arnabaldi, C; Bellunato, T F; Calvi, M; Matteuzzi, C; Musy, M; Negri, P; Perego, D L; Pessina, G; Chamonal, R; Eisenhardt, S; Lawrence, J; McCarron, J; Muheim, F; Playfer, S; Walker, A; Cuneo, S; Fontanelli, F; Gracco, Valerio; Mini, G; Musico, P; Petrolini, A; Sannino, M; Bates, A; MacGregor, A; O'Shea, V; Parkes, C; Paterson, S; Petrie, D; Pickford, A; Rahman, M; Soler, F; Allebone, L; Barber, J H; Cameron, W; Clark, D; Dornan, Peter John; Duane, A; Egede, U; Hallam, R; Howard, A; Plackett, R; Price, D; Savidge, T; Vidal-Sitjes, G; Websdale, D M; Adinolfi, M; Bibby, J H; Cioffi, C; Gligorov, Vladimir V; Harnew, N; Harris, F; McArthur, I A; Newby, C; Ottewell, B; Rademacker, J; Senanayake, R; Somerville, L P; Soroko, A; Smale, N J; Topp-Jørgensen, S; Wilkinson, G; Yang, S; Benayoun, M; Khmelnikov, V A; Obraztsov, V F; Densham, C J; Easo, S; Franek, B; Kuznetsov, G; Loveridge, P W; Morrow, D; Morris, JV; Papanestis, A; Patrick, G N; Woodward, M L; Aglieri-Rinella, G; Albrecht, A; Braem, André; Campbell, M; D'Ambrosio, C; Forty, R W; Frei, C; Gys, Thierry; Jamet, O; Kanaya, N; Losasso, M; Moritz, M; Patel, M; Piedigrossi, D; Snoeys, W; Ullaland, O; Van Lysebetten, A; Wyllie, K

    2005-01-01

    This document describes the concepts of the engineering design to be adopted for the upstream Ring Imaging Cherenkov detector (RICH1) of the reoptimized LHCb detector. Our aim is to ensure that coherent solutions for the engineering design and integration for all components of RICH1 are available, before proceeding with the detailed design of these components.

  14. Design review of the SYVAC Executive

    International Nuclear Information System (INIS)

    Lane, G.D.

    1985-01-01

    The report documents the current SYVAC Executive design. Eight criteria for evaluating aspects of the design as objectively as possible are described as well as the results of applying them. Principal benefits arising from implementation of design recommendations are perceived to be improved maintainability and better delineation of the interface between the Executive and SYVAC submodels. (author)

  15. 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

  16. 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)

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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)

  2. 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…

  3. 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

  4. 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.

  5. 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

  6. Engineering Changes in Product Design - A Review

    Science.gov (United States)

    Karthik, K.; Janardhan Reddy, K., Dr

    2016-09-01

    Changes are fundamental to product development. Engineering changes are unavoidable and can arise at any phase of the product life cycle. The consideration of market requirements, customer/user feedbacks, manufacturing constraints, design innovations etc., turning them into viable products can be accomplished when product change is managed properly. In the early design cycle, informal changes are accepted. However, changes become formal when its complexity and cost increases, and as product matures. To maximize the market shares, manufacturers have to effectively and efficiently manage engineering changes by means of Configuration Control. The paper gives a broad overview about ‘Engineering Change Management’ (ECM) through configuration management and its implications in product design. The aim is to give an idea and understanding about the engineering changes in product design scenario to the new researchers. This paper elaborates the significant aspect of managing the engineering changes and the importance of ECM in a product life cycle.

  7. TPX: Contractor preliminary design review. Volume 3, Design and analysis

    International Nuclear Information System (INIS)

    1995-01-01

    Several models have been formed for investigating the maximum electromagnetic loading and magnetic field levels associated with the Tokamak Physics eXperiment (TPX) superconducting Poloidal Field (PF) coils. The analyses have been performed to support the design of the individual fourteen hoop coils forming the PF system. The coils have been sub-divided into three coil systems consisting of the central solenoid (CS), PF5 coils, and the larger radius PF6 and PF7 coils. Various electromagnetic analyses have been performed to determine the electromagnetic loadings that the coils will experience during normal operating conditions, plasma disruptions, and fault conditions. The loadings are presented as net body forces acting individual coils, spatial variations throughout the coil cross section, and force variations along the path of the conductor due to interactions with the TF coils. Three refined electromagnetic models of the PF coil system that include a turn-by-turn description of the fields and forces during a worst case event are presented in this report. A global model including both the TF and PF system was formed to obtain the force variations along the path of the PF conductors resulting from interactions with the TF currents. In addition to spatial variations, the loadings are further subdivided into time-varying and steady components so that structural fatigue issues can be addressed by designers and analysts. Other electromagnetic design issues such as the impact of the detailed coil designs on field errors are addressed in this report. Coil features that are analyzed include radial transitions via short jogs vs. spiral type windings and the effects of layer-to-layer rotations (i.e clocking) on the field errors

  8. TPX: Contractor preliminary design review. Volume 3, Design and analysis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-30

    Several models have been formed for investigating the maximum electromagnetic loading and magnetic field levels associated with the Tokamak Physics eXperiment (TPX) superconducting Poloidal Field (PF) coils. The analyses have been performed to support the design of the individual fourteen hoop coils forming the PF system. The coils have been sub-divided into three coil systems consisting of the central solenoid (CS), PF5 coils, and the larger radius PF6 and PF7 coils. Various electromagnetic analyses have been performed to determine the electromagnetic loadings that the coils will experience during normal operating conditions, plasma disruptions, and fault conditions. The loadings are presented as net body forces acting individual coils, spatial variations throughout the coil cross section, and force variations along the path of the conductor due to interactions with the TF coils. Three refined electromagnetic models of the PF coil system that include a turn-by-turn description of the fields and forces during a worst case event are presented in this report. A global model including both the TF and PF system was formed to obtain the force variations along the path of the PF conductors resulting from interactions with the TF currents. In addition to spatial variations, the loadings are further subdivided into time-varying and steady components so that structural fatigue issues can be addressed by designers and analysts. Other electromagnetic design issues such as the impact of the detailed coil designs on field errors are addressed in this report. Coil features that are analyzed include radial transitions via short jogs vs. spiral type windings and the effects of layer-to-layer rotations (i.e clocking) on the field errors.

  9. 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)

  10. 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

  11. Review of nuclear piping seismic design requirements

    International Nuclear Information System (INIS)

    Slagis, G.C.; Moore, S.E.

    1994-01-01

    Modern-day nuclear plant piping systems are designed with a large number of seismic supports and snubbers that may be detrimental to plant reliability. Experimental tests have demonstrated the inherent ruggedness of ductile steel piping for seismic loading. Present methods to predict seismic loads on piping are based on linear-elastic analysis methods with low damping. These methods overpredict the seismic response of ductile steel pipe. Section III of the ASME Boiler and Pressure Vessel Code stresses limits for piping systems that are based on considerations of static loads and hence are overly conservative. Appropriate stress limits for seismic loads on piping should be incorporated into the code to allow more flexible piping designs. The existing requirements and methods for seismic design of piping systems, including inherent conservations, are explained to provide a technical foundation for modifications to those requirements. 30 refs., 5 figs., 3 tabs

  12. 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.

  13. 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.

  14. 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.

  15. 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

  16. 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

  17. 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

  18. An ALARA-conscious hot particle control program

    International Nuclear Information System (INIS)

    Doolittle, W.W.; Bredvad, R.S.; Bevelacqua, J.J.

    1992-01-01

    In 1989 approximately twenty-five percent of the radiation dose received by the Point Beach Nuclear Plant (PBNP) Health Physics group was due to its hot particle control program. The Health Physics group initiated a review of the program with the objective of decreasing the dose expenditure for hot particle control while maintaining a high standard for hot particle detection and control. In this paper the methods and results of this evaluation are described. The components of the hot particle control program, rules of thumb, and radionuclide composition at PBNP are presented

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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....

  9. 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.

  10. 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)

  11. 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

  12. 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 ...

  13. 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...

  14. 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

  15. 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

  16. Transportation ALARA analysis for a nuclear waste management system

    International Nuclear Information System (INIS)

    McNair, G. W.; Schneider, K.; Smith, R.I.; Ross, W.; Faletti, D.

    1988-01-01

    In planning for implementation of a safe and cost-effective transportation system, the Department of Energy (DOE) commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the radiation doses, both public and occupational, that would result from operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in relatively high doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. This study contains an analysis of routine operations and estimates of the public and worker radiation doses that would occur in a postulated generic reference spent fuel transportation system using both truck and rail modes. Total risks are not estimated (i.e., consideration of nonradiological or accident risks that will be the subject of future studies in the transportation systems study plan 9TSSP) are not included). The system encompasses spent fuel loading at the reactor, transportation of the fuel to and from a receiving and handling facility and unloading of the fuel at a repository. The analysis provides cost/dose trade-offs of the postulated reference system as well as selected potential alternatives to the transportation system

  17. 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.

  18. 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

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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)

  7. 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.

  8. 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.

  9. 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)

  10. 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.

  11. 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

  12. 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

  13. 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.

  14. 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.

  15. 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.

  16. 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

  17. 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

  18. 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)

  19. 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.

  20. 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.

  1. Adaptive design methods in clinical trials – a review

    Directory of Open Access Journals (Sweden)

    Chang Mark

    2008-05-01

    Full Text Available Abstract In recent years, the use of adaptive design methods in clinical research and development based on accrued data has become very popular due to its flexibility and efficiency. Based on adaptations applied, adaptive designs can be classified into three categories: prospective, concurrent (ad hoc, and retrospective adaptive designs. An adaptive design allows modifications made to trial and/or statistical procedures of ongoing clinical trials. However, it is a concern that the actual patient population after the adaptations could deviate from the originally target patient population and consequently the overall type I error (to erroneously claim efficacy for an infective drug rate may not be controlled. In addition, major adaptations of trial and/or statistical procedures of on-going trials may result in a totally different trial that is unable to address the scientific/medical questions the trial intends to answer. In this article, several commonly considered adaptive designs in clinical trials are reviewed. Impacts of ad hoc adaptations (protocol amendments, challenges in by design (prospective adaptations, and obstacles of retrospective adaptations are described. Strategies for the use of adaptive design in clinical development of rare diseases are discussed. Some examples concerning the development of Velcade intended for multiple myeloma and non-Hodgkin's lymphoma are given. Practical issues that are commonly encountered when implementing adaptive design methods in clinical trials are also discussed.

  2. Design for Sustainability and Project Management Literature – A Review

    DEFF Research Database (Denmark)

    Ali, Faheem; Boks, Casper; Bey, Niki

    2016-01-01

    management literature has hardly been considered in design for sustainability research, this article attempts to review the points of intersection between these two fields, and explores the potential that knowledge from project management literature has in improving efficiency and effectiveness...... of development and implementation of design for sustainability tools.......The growing pressure on natural resources and increasing global trade have made sustainability issues a prime area of concern for all businesses alike. The increased focus on sustainability has impacted the way projects are conceived, planned, executed and evaluated in industries. Since project...

  3. 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...

  4. 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.

  5. Prestressed concrete reactor vessels: review of design and failure criteria

    International Nuclear Information System (INIS)

    Endebrock, E.G.

    1975-03-01

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

  6. 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

  7. 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.

  8. Automotive HMI design and participatory user involvement: review and perspectives.

    Science.gov (United States)

    François, Mathilde; Osiurak, François; Fort, Alexandra; Crave, Philippe; Navarro, Jordan

    2017-04-01

    Automotive human-machine interface (HMI) design is facing new challenges due to the technological advances of the last decades. The design process has to be adapted in order to address human factors and road safety challenges. It is now widely accepted that user involvement in the HMI design process is valuable. However, the current form of user involvement in industry remains at the stages of concept assessment and usability tests. Moreover, the literature in other fields (e.g. information systems) promotes a broader user involvement with participatory design (i.e. the user is fully involved in the development process). This article reviews the established benefits of participatory design and reveals perspectives for automotive HMI quality improvement in a cognitive ergonomic framework. Practitioner Summary: Automotive HMI quality determines, in part, drivers' ability to perform primary driving tasks while using in-vehicle devices. User involvement in the design process is a key point to contribute to HMI quality. This article reports the potential benefits of a broad involvement from drivers to meet automotive HMI design challenges.

  9. The application of ALARA to the design and operation of the U.K. PWR

    International Nuclear Information System (INIS)

    Pepper, R.B.; Dutton, L.M.C.

    1984-01-01

    When operating a nuclear establishment, the Central Electricity Generating Board (CEGB) is required to conform with all the requirements of national legislation. In term of radiological protection, this essentially means that the requirements of ICRP 26 must be met. The three main precepts of ICRP 26 are: (i) no practice shall be adopted unless its introduction produce a positive net benefit; (ii) all exposure shall be kept as low as reasonably achievable, economic and social factors being taken into account; and (iii) the effective dose-equivalent to individuals shall not exceed the limits recommended for the appropriate circumstances by the Commission. This paper is concerned with compliance with the second of the above requirements

  10. Implementation of ALARA at the design stage of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Brissaud, A.; Ridoux, P. [Electricite de France, Villeurbanne (France)

    1995-03-01

    In the 1970s, Electricite de France (EdF) had limited knowledge and experience of pressurized water reactors (PWRs). Electricity generation by nuclear units was oriented towards gas-graphite reactors, even though EdF had a share in the PWR unit of CHOOZ A-1 (250 MWe, later upgraded to 320 MWe). Some facts about the origin of doses in that king of reactor were known to the research and development (R&D) support staff of EdF, which mainly comprises the French Atomic Commission (CEA), but only a few of EdF`s engineers were aware of these facts. One has to bear in mind that CHOOZ A-1 only went critical in April 1967 and was officially connected to the grid in May 1970 after some important problems had been solved. Meanwhile, the nuclear program was launched at full speed, beginning with the order for FESSENHEIM 1 in 1970, FESSENHEIM 2 and BUGEY 2 and 3 in 1971. TIHANGE 1, in which EdF had a share, went on-line in September 1975. Also, supposing that EdF had had such knowledge and experience, it is quite evident that it would have been very difficult to modify the lay-out inside the reactor building.

  11. 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

  12. 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

  13. 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.

  14. 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)

  15. 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

  16. 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)

  17. 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

  18. 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)

  19. 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)

  20. 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

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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.

  11. Advanced control room design review guidelines: Merging old and new

    International Nuclear Information System (INIS)

    Carter, R.J.; Wachtel, J.A.

    1992-01-01

    The nuclear power industry is currently developing operator interface systems based on innovative applications of digital computers. To assure that this advanced technology is incorporated in a way that maximizes the potential safety benefits of the technology and minimizes the potential negative effects on human performance, human factors principles must be considered. NUREG-0700 contains guidelines for the review of operator interfaces. However, in light of the rapid technological advances in digital technology which have taken place in the eleven years since its publication, it is no longer adequate to assess the rapidly changing human-system interfaces. A research program, the purpose of which is to upgrade NUREG-0700, has been initiated. Thus far a set of draft advanced control room design review (ACRDR) guidelines has been complied. Three tasks, which were oriented towards integrating the applicable guidelines in NUREG-0700 into the ACRDR document, are described in the paper

  12. Tritium Systems Test Assembly: design for major device fabrication review

    International Nuclear Information System (INIS)

    Anderson, J.L.; Sherman, R.H.

    1977-06-01

    This document has been prepared for the Major Device Fabrication Review for the Tritium Systems Test Assembly (TSTA). The TSTA is dedicated to the development, demonstration, and interfacing of technologies related to the deuterium-tritium fuel cycle for fusion reactor systems. The principal objectives for TSTA are: (a) demonstrate the fuel cycle for fusion reactor systems; (b) develop test and qualify equipment for tritium service in the fusion program; (c) develop and test environmental and personnel protective systems; (d) evaluate long-term reliability of components; (e) demonstrate long-term safe handling of tritium with no major releases or incidents; and (f) investigate and evaluate the response of the fuel cycle and environmental packages to normal, off-normal, and emergency situations. This document presents the current status of a conceptual design and cost estimate for TSTA. The total cost to design, construct, and operate TSTA through FY-1981 is estimated to be approximately $12.2 M

  13. Carbon Taxes. A Review of Experience and Policy Design Considerations

    Energy Technology Data Exchange (ETDEWEB)

    Sumner, Jenny [National Renewable Energy Lab. (NREL), Golden, CO (United States); Bird, Lori [National Renewable Energy Lab. (NREL), Golden, CO (United States); Smith, Hillary [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2009-12-01

    State and local governments in the United States are evaluating a wide range of policies to reduce carbon emissions, including, in some instances, carbon taxes, which have existed internationally for nearly 20 years. This report reviews existing carbon tax policies both internationally and in the United States. It also analyzes carbon policy design and effectiveness. Design considerations include which sectors to tax, where to set the tax rate, how to use tax revenues, what the impact will be on consumers, and how to ensure emissions reduction goals are achieved. Emission reductions that are due to carbon taxes can be difficult to measure, though some jurisdictions have quantified reductions in overall emissions and other jurisdictions have examined impacts that are due to programs funded by carbon tax revenues.

  14. Carbon Taxes: A Review of Experience and Policy Design Considerations

    Energy Technology Data Exchange (ETDEWEB)

    Sumner, J.; Bird, L.; Smith, H.

    2009-12-01

    State and local governments in the United States are evaluating a wide range of policies to reduce carbon emissions, including, in some instances, carbon taxes, which have existed internationally for nearly 20 years. This report reviews existing carbon tax policies both internationally and in the United States. It also analyzes carbon policy design and effectiveness. Design considerations include which sectors to tax, where to set the tax rate, how to use tax revenues, what the impact will be on consumers, and how to ensure emissions reduction goals are achieved. Emission reductions that are due to carbon taxes can be difficult to measure, though some jurisdictions have quantified reductions in overall emissions and other jurisdictions have examined impacts that are due to programs funded by carbon tax revenues.

  15. Business Process Design Of An Efficient And Effective Literature Review

    Directory of Open Access Journals (Sweden)

    Sayuthi

    2015-08-01

    Full Text Available The objective of this articleis to design business processesan organization efficiently and effectively. Based on our literature review the design of business processes that is best suitable for an organization belongs to Harrington 1992 namely the concept of Business Process Improvement BPI which is a systematic framework that helps organizations in making significant progress in the implementation of business processes. BPI provides a system that will simplify or streamline business processes to provide an assurance that the internal and external customers of the organization will get a better output. One advantage of BPI concept suggested by Harrington is the continuous improvement whereas the other authorsor experts of BPI have not recognize the idea of continuous improvement. With thisidea the products services offered by organization becomes more innovative.

  16. 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

  17. Actinic Mask Inspection at the ALS Initial Design Review

    International Nuclear Information System (INIS)

    Barty, A; Chapman, H; Sweeney, D; Levesque, R; Bokor, J; Gullikson, E; Jong, S; Liu, Y; Yi, M; Denbeaux, G; Goldberg, K; Naulleau, P; Denham, P; Rekawa, S; Baston, P; Tackaberry, R; Barale, P

    2003-01-01

    This report is the first milestone report for the actinic mask blank inspection project conducted at the VNL, which forms sub-section 3 of the Q1 2003 mask blank technology transfer program at the VNL. Specifically this report addresses deliverable 3.1.1--design review and preliminary tool design. The goal of this project is to design an actinic mask inspection tool capable of operating in two modes: high-speed scanning for the detection of multilayer defects (inspection mode), and a high-resolution aerial image mode in which the image emulates the imaging illumination conditions of a stepper system (aerial image or AIM mode). The purpose and objective of these two modes is as follows: (1) Defect inspection mode--This imaging mode is designed to scan large areas of the mask for defects EUV multilayer coatings. The goal is to detect the presence of multilayer defects on a mask blank and to store the co-ordinates for subsequent review in AIM mode, thus it is not essential that the illumination and imaging conditions match that of a production stepper. Potential uses for this imaging mode include: (a) Correlating the results obtained using actinic inspection with results obtained using other non-EUV defect inspection systems to verify that the non-EUV scanning systems are detecting all critical defects; (b) Gaining sufficient information to associate defects with particular processes, such as various stages of the multilayer deposition or different modes of operation of the deposition tool; and (c) Assessing the density and EUV impact of surface and multilayer anomalies. Because of the low defect density achieved using current multilayer coating technology it is necessary to be able to efficiently scan large areas of the mask in order to obtain sufficient statistics for use in cross-correlation experiments. Speed of operation as well as sensitivity is therefore key to operation in defect inspection mode. (2) Aerial Image Microscope (AIM) mode--In AIM mode the tool is

  18. Nuclear renaissance, public perception and design criteria: An exploratory review

    International Nuclear Information System (INIS)

    Goodfellow, Martin J.; Williams, Hugo R.; Azapagic, Adisa

    2011-01-01

    There is currently an international drive to build new nuclear power plants, bringing about what is being termed a 'nuclear renaissance'. However, the public perception of nuclear energy has historically been, and continues to be, a key issue, particularly in light of the Fukushima nuclear incident. This paper discusses the disparity between perceived and calculated risks based on the last four decades of research into risk perception. The leading psychological and sociological theories, Psychometric Paradigm and Cultural Theory, respectively, are critically reviewed. The authors then argue that a new nuclear-build policy that promotes a broader approach to design incorporating a wider range of stakeholder inputs, including that of the lay public, may provide a means for reducing the perceived risk of a nuclear plant. Further research towards such a new approach to design is proposed, based on integrating expert and lay stakeholder inputs and taking into account broader socio-cultural factors whilst maintaining the necessary emphasis on safety, technological development, economics and environmental sustainability. - Highlights: → Globally, a number of countries are investing in or considering building new nuclear plants. → Public acceptance of nuclear safety is important to continuing new nuclear build efforts. → Theories are discussed attempting to explain the public perception of nuclear safety. → A socially informed design process is proposed which could assist in ensuring public support. → Further research to understand how this design process might be performed is proposed.

  19. Computational approaches in the design of synthetic receptors - A review.

    Science.gov (United States)

    Cowen, Todd; Karim, Kal; Piletsky, Sergey

    2016-09-14

    The rational design of molecularly imprinted polymers (MIPs) has been a major contributor to their reputation as "plastic antibodies" - high affinity robust synthetic receptors which can be optimally designed, and produced for a much reduced cost than their biological equivalents. Computational design has become a routine procedure in the production of MIPs, and has led to major advances in functional monomer screening, selection of cross-linker and solvent, optimisation of monomer(s)-template ratio and selectivity analysis. In this review the various computational methods will be discussed with reference to all the published relevant literature since the end of 2013, with each article described by the target molecule, the computational approach applied (whether molecular mechanics/molecular dynamics, semi-empirical quantum mechanics, ab initio quantum mechanics (Hartree-Fock, Møller-Plesset, etc.) or DFT) and the purpose for which they were used. Detailed analysis is given to novel techniques including analysis of polymer binding sites, the use of novel screening programs and simulations of MIP polymerisation reaction. The further advances in molecular modelling and computational design of synthetic receptors in particular will have serious impact on the future of nanotechnology and biotechnology, permitting the further translation of MIPs into the realms of analytics and medical technology. Copyright © 2016 Elsevier B.V. All rights reserved.

  20. Review of SFR Design Safety using Preliminary Regulatory PSA Model

    International Nuclear Information System (INIS)

    Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

    2013-01-01

    The major objective of this research is to develop a risk model for regulatory verification of the SFR design, and thereby, make sure that the SFR design is adequate from a risk perspective. In this paper, the development result of preliminary regulatory PSA model of SFR is discussed. In this paper, development and quantification result of preliminary regulatory PSA model of SFR is discussed. It was confirmed that the importance PDRC and ADRC dampers is significant as stated in the result of KAERI PSA model. However, the importance can be changed significantly depending on assumption of CCCG and CCF factor of PDRC and ADRC dampers. SFR (sodium-cooled fast reactor) which is Gen-IV nuclear energy system, is designed to accord with the concept of stability, sustainability and proliferation resistance. KALIMER-600, which is under development in Korea, includes passive safety systems (e. g. passive reactor shutdown, passive residual heat removal, and etc.) as well as active safety systems. Risk analysis from a regulatory perspective is needed to support the regulatory body in its safety and licensing review for SFR (KALIMER-600). Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and delay of the SFR licensing schedule that may be caused otherwise

  1. 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

  2. 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)

  3. 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

  4. 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

  5. Designer Drugs: A Review of Literature Abdulsallam Bakdash

    Directory of Open Access Journals (Sweden)

    Abdulsallam Bakdash

    2015-05-01

    Full Text Available A new phenomenon in the drug market has appeared in recent years: there has been an increase in the number and types of designer drugs. A massive influx of these structural and/or functional analogs of controlled substances has resulted in an increase in their marketing and abuse. At present, these drugs are significantly more widely available compared to previous years because they are relatively inexpensive and marketed as being safer than classic drugs of abuse. The most important factor in the spread of designer drugs is that the majority of these substances are undetectable as drugs or illegal drugs in standard drug testing procedures. The biological effects of these substances are largely unknown to both users and medical scientists. However, most known cases of abuse have shown serious and dangerous physical and psychological reactions in users. The manufacturing and marketing of designer drugs presents a major challenge for specialist sectors, especially laboratories that have to test these substances. This highlights the important role of drugcontrol institutions and regulatory and legislative bodies to determine the legal status of these drugs, which are designed and marketed - mostly through the internet - as being legal. All of these factors make it incumbent upon these sectors to form a unified goal and strategy to control these substances and prevent their spread. This review provides fundamental information about designer drugs. This will provide an accurate overview of their status, and will aid future work to develop a regulatory and legislative strategy to combat their manufacture, marketing, and use.

  6. 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

  7. 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

  8. 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.

  9. 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.

  10. Green perspective in food industry production line design: A review

    Science.gov (United States)

    Xian, C. Y.; Sin, T. C.; Liyana, M. R. N.; Awang, A.; Fathullah, M.

    2017-09-01

    The design of green manufacturing process in food industries is currently a hot research topic in the multidisciplinary area of applied chemistry, biology and technology. Several process such as freezing, cutting, drying, tempering, bleaching, sterilization, extraction and filtering have been applied efficiency in the food industry. Due to the rapid development of food and peripheral technology, the use of new physical processing or auxiliary processing methods can maintain food inherent nutrients, texture, color, and freshness and also reduce environmental pollution and energy consumption in food processing. Hence, this review paper will study and summarize the effects of green manufacturing process in food industries in term of waste reduction, materials and sustainability manufacturing. In any case, All the food processing equipment must comply with strict standards and regulation, this action will ensure the securing the food quality and safety of food products to consumers.

  11. REVIEW KONSEP RESPONSIVE DESIGN DENGAN FRAMEWORK MATERIALIZE PADA WEBSITE

    Directory of Open Access Journals (Sweden)

    Cindy Novianty

    2017-09-01

    Full Text Available Responsive web design merupakan sebuah desain website yang dapat menyesuaikan tiap ukuran pada tiap device. Berdasarkan hasil dari beberapa responden menyatakan 62% responden setuju jika beberapa website yang belum mampu menyesuaikan ukuran tampilan web, 54% responden setuju bahwa desain yang responsive mempengaruhi faktor kenyamanan responden, 60% responden setuju bahwa konten utama dan fungsionalitas dari website yang sulit diakses melalui perangkat mobile, 56% responden setuju bahwa tampilan website yang kurang responsive berpengaruh buruk terhadap faktor kenyamanan responden, 52% responden setuju bahwa website yang belum mampu menyesuaikan ukuran pada tiap perangkat mobile. Dari hasil review tersebut dapat disimpulkan bahwa website yang tidak responsive mempengaruhi ketidak nyamanan para pengguna untuk mengakses informasi melalui website online.

  12. Classifications, applications, and design challenges of drones: A review

    Science.gov (United States)

    Hassanalian, M.; Abdelkefi, A.

    2017-05-01

    Nowadays, there is a growing need for flying drones with diverse capabilities for both civilian and military applications. There is also a significant interest in the development of novel drones which can autonomously fly in different environments and locations and can perform various missions. In the past decade, the broad spectrum of applications of these drones has received most attention which led to the invention of various types of drones with different sizes and weights. In this review paper, we identify a novel classification of flying drones that ranges from unmanned air vehicles to smart dusts at both ends of this spectrum, with their new defined applications. Design and fabrication challenges of micro drones, existing methods for increasing their endurance, and various navigation and control approaches are discussed in details. Limitations of the existing drones, proposed solutions for the next generation of drones, and recommendations are also presented and discussed.

  13. 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.

  14. Nutrition by design: a review of biotechnology in functional food

    Directory of Open Access Journals (Sweden)

    Thomas Reynolds

    2016-02-01

    Full Text Available Medical institutions in industrial and developing countries are increasingly turning to functional foods as intervention in chronic disease. Advances in genetic engineering have provided methods of purposefully designing functional foods and bioactive compound-producing organisms. This literature review examines the recent history of biotechnological applications in functional food, the state of bioagricultural engineering for high-value compound production, and the challenges that developers face in promulgatingfunctional foods from biotechnological sources. Based on the literature reviewed, it is predicted that adding biotechnologically-produced compounds will be more successful in producing novel functional foods. Conclusion: Current functional food application is frequently hampered by a dearth of foods suitable to the purpose. The concurrent advent of biotechnology means that producers and clinicians are not constrained by limited and precarious natural development. Biotechnology has already produced altered dietary staples that can safely induce real health benefits, but the social approval of genetically modified foodstuffs is inconsistent at best. Modifying microalgae to produce micro and macronutrients, for harvest and incorporation into functional food products, provides the ideal specificity and reliability for bioactive compound use. However, its application in biomedical science is impeded by technical difficulty. It remains to be seen if microorganism engineering willbe able to meet the needs of its many stakeholders, including the functional food community. Nonetheless,the prospect of a flourishing functional food market, and the healthier population it will bring about, certainly makes it worth a try.

  15. A REVIEW OF MILD COMBUSTION AND OPEN FURNACE DESIGN CONSIDERATION

    Directory of Open Access Journals (Sweden)

    M.M. Noor

    2012-12-01

    Full Text Available Combustion is still very important to generate energy. Moderate or Intense Low-oxygen Dilution (MILD combustion is one of the best new technologies for clean and efficient combustion. MILD combustion has been proven to be a promising combustion technology in industrial applications with decreased energy consumption due to the uniformity of its temperature distribution. It is clean compared to traditional combustion due to producing low NOx and CO emissions. This article provides a review and discussion of recent research and developments in MILD. The issue and applications are summarized, with some suggestions presented on the upgrading and application of MILD in the future. Currently MILD combustion has been successfully applied in closed furnaces. The preheating of supply air is no longer required since the recirculation inside the enclosed furnace already self-preheats the supply air and self-dilutes the oxygen in the combustion chamber. The possibility of using open furnace MILD combustion will be reviewed. The design consideration for open furnace with exhaust gas re-circulation (EGR was discussed.

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. Optimization of infobutton design and Implementation: A systematic review.

    Science.gov (United States)

    Teixeira, Miguel; Cook, David A; Heale, Bret S E; Del Fiol, Guilherme

    2017-10-01

    Infobuttons are clinical decision tools embedded in the electronic health record that attempt to link clinical data with context sensitive knowledge resources. We systematically reviewed technical approaches that contribute to improved infobutton design, implementation and functionality. We searched databases including MEDLINE, EMBASE, and the Cochrane Library database from inception to March 1, 2016 for studies describing the use of infobuttons. We selected full review comparative studies, usability studies, and qualitative studies examining infobutton design and implementation. We abstracted usability measures such as user satisfaction, impact, and efficiency, as well as prediction accuracy of infobutton content retrieval algorithms and infobutton adoption/interoperability. We found 82 original research studies on infobuttons. Twelve studies met criteria for detailed abstraction. These studies investigated infobutton interoperability (1 study); tools to help tailor infobutton functionality (1 study); interventions to improve user experience (7 studies); and interventions to improve content retrieval by improving prediction of relevant knowledge resources and information needs (3 studies). In-depth interviews with implementers showed the Health Level Seven (HL7) Infobutton standard to be simple and easy to implement. A usability study demonstrated the feasibility of a tool to help medical librarians tailor infobutton functionality. User experience studies showed that access to resources with which users are familiar increased user satisfaction ratings; and that links to specific subsections of drug monographs increased information seeking efficiency. However, none of the user experience improvements led to increased usage uptake. Recommender systems based on machine learning algorithms outperformed hand-crafted rules in the prediction of relevant resources and clinicians' information needs in a laboratory setting, but no studies were found using these techniques

  1. 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

  2. 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

  3. 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…

  4. Design review of the Brazilian Experimental Solar Telescope

    Science.gov (United States)

    Dal Lago, A.; Vieira, L. E. A.; Albuquerque, B.; Castilho, B.; Guarnieri, F. L.; Cardoso, F. R.; Guerrero, G.; Rodríguez, J. M.; Santos, J.; Costa, J. E. R.; Palacios, J.; da Silva, L.; Alves, L. R.; Costa, L. L.; Sampaio, M.; Dias Silveira, M. V.; Domingues, M. O.; Rockenbach, M.; Aquino, M. C. O.; Soares, M. C. R.; Barbosa, M. J.; Mendes, O., Jr.; Jauer, P. R.; Branco, R.; Dallaqua, R.; Stekel, T. R. C.; Pinto, T. S. N.; Menconi, V. E.; Souza, V. M. C. E. S.; Gonzalez, W.; Rigozo, N.

    2015-12-01

    The Brazilian's National Institute for Space Research (INPE), in collaboration with the Engineering School of Lorena/University of São Paulo (EEL/USP), the Federal University of Minas Gerais (UFMG), and the Brazilian's National Laboratory for Astrophysics (LNA), is developing a solar vector magnetograph and visible-light imager to study solar processes through observations of the solar surface magnetic field. The Brazilian Experimental Solar Telescope is designed to obtain full disk magnetic field and line-of-sight velocity observations in the photosphere. Here we discuss the system requirements and the first design review of the instrument. The instrument is composed by a Ritchey-Chrétien telescope with a 500 mm aperture and 4000 mm focal length. LCD polarization modulators will be employed for the polarization analysis and a tuning Fabry-Perot filter for the wavelength scanning near the Fe II 630.25 nm line. Two large field-of-view, high-resolution 5.5 megapixel sCMOS cameras will be employed as sensors. Additionally, we describe the project management and system engineering approaches employed in this project. As the magnetic field anchored at the solar surface produces most of the structures and energetic events in the upper solar atmosphere and significantly influences the heliosphere, the development of this instrument plays an important role in advancing scientific knowledge in this field. In particular, the Brazilian's Space Weather program will benefit most from the development of this technology. We expect that this project will be the starting point to establish a strong research program on Solar Physics in Brazil. Our main aim is to progressively acquire the know-how to build state-of-art solar vector magnetograph and visible-light imagers for space-based platforms.

  5. The platform shapes the message : How website design affects abstraction and valence of online consumer reviews

    NARCIS (Netherlands)

    Aerts, Goele; Smits, Tim; Verlegh, Peeter W.J.

    2017-01-01

    Online consumer reviews provide relevant information about products and services for consumers. In today's networked age, the online consumer review platform market is hyper-competitive. These platforms can easily change different design characteristics to get more reviewers and to nudge reviewers

  6. 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...

  7. 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…

  8. 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

  9. 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.

  10. 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

  11. 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

  12. Design review report for the MCO loading system

    Energy Technology Data Exchange (ETDEWEB)

    Brisbin, S.A.

    1997-06-23

    This design report presents the 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.

  13. Design review report for the MCO loading system

    International Nuclear Information System (INIS)

    Brisbin, S.A.

    1997-01-01

    This design report presents the 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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.

  19. 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

  20. A review on the lattice design of large hadron colliders

    International Nuclear Information System (INIS)

    Lee, S.Y.

    1987-01-01

    The conceptual evolution of the accelerator lattice design is discussed. Indicated are aspects of IR design. We emphasize the cancellation of stop-band width in the cluster design. The case of symmetric vs antisymmetric design is also discussed. The SSC lattice is used as an example. 9 refs

  1. Urinary Tract Infection Antibiotic Trial Study Design: A Systematic Review.

    Science.gov (United States)

    Basmaci, Romain; Vazouras, Konstantinos; Bielicki, Julia; Folgori, Laura; Hsia, Yingfen; Zaoutis, Theoklis; Sharland, Mike

    2017-12-01

    Urinary tract infections (UTIs) represent common bacterial infections in children. No guidance on the conduct of pediatric febrile UTI clinical trials (CTs) exist. To assess the criteria used for patient selection and the efficacy end points in febrile pediatric UTI CTs. Medline, Embase, Cochrane central databases, and clinicaltrials.gov were searched between January 1, 1990, and November 24, 2016. We combined Medical Subject Headings terms and free-text terms for "urinary tract infections" and "therapeutics" and "clinical trials" in children (0-18 years), identifying 3086 articles. Two independent reviewers assessed study quality and performed data extraction. We included 40 CTs in which a total of 4381 cases of pediatric UTIs were investigated. Positive urine culture results and fever were the most common inclusion criteria (93% and 78%, respectively). Urine sampling method, pyuria, and colony thresholds were highly variable. Clinical and microbiological end points were assessed in 88% and 93% of the studies, respectively. Timing for end point assessment was highly variable, and only 3 studies (17%) out of the 18 performed after the Food and Drug Administration 1998 guidance publication assessed primary and secondary end points consistently with this guidance. Our limitations included a mixed population of healthy children and children with an underlying condition. In 6 trials, researchers studied a subgroup of patients with afebrile UTI. We observed a wide variability in the microbiological inclusion criteria and the timing for end point assessment. The available guidance for adults appear not to be used by pediatricians and do not seem applicable to the childhood UTI. A harmonized design for pediatric UTIs CT is necessary. Copyright © 2017 by the American Academy of Pediatrics.

  2. 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.

  3. Left ventricular assist device (lvad design features: literature review

    Directory of Open Access Journals (Sweden)

    Yu. V. Bogdanova

    2014-01-01

    long-term systems of artificial circulatory support is guided by German Heart Center in Berlin (DHZB [3].The well-known VAD commercial models were created by Berlin Heart (Germany, HeartWare Int. (USA, Thoratec (USA, Abiomed Inc. (USA etc.Works devoted to VAD systems can be classified in field of research, according to the above subsystems. Concerning the blood pump - a large number of works is devoted to the study of blood behavior in the pump chamber: to modeling questions [6-24], with an emphasis on red blood cells damage - hemolysis [10, 20, 23, 27-32]. Much less works are devoted to the research of rotor (impeller dynamics of the blood pump [33-36]. Application of magnetic bearings in VAD and magnetic levitation control tasks of are addressed in [33-39]. Biomedical part of design, associated with the selection and development of biocompatible materials is considered in [26, 32, 40-43]. Features of power supply systems and control of VAD mode work are given in works [26, 44-50].The integrated approach to VAD development with an emphasis on design phases is presented in the works [7, 51]. In [2] the problem of artificial heart creation in Russia on 2006 is clearly reflected. The most comprehensive systematic review of existing VAD systems with description of specifications is given in the work [54], as well as in [24, 26, 55-57]. Brief review of existing methodologies and approaches to the design of artificial heart (AH and circulatory support system (CSS are presented in the works [58, 59]. The problem of creation of mechatronic modules of AH and CSS systems is studied in [60, 61].With the purpose of further research in the development of VAD system, this work is the study of up to date problem state. The main part of the work consists of three sections. The first section is devoted to the study of blood pump. The second and the third sections are devoted to power supply system and control system respectively. Based on this analysis, the requirements to VAD

  4. Review and comparison of magnet designs for magnetic refrigeration

    DEFF Research Database (Denmark)

    Bjørk, Rasmus; Bahl, Christian Robert Haffenden; Smith, Anders

    2010-01-01

    One of the key issues in magnetic refrigeration is generating the magnetic field that the magnetocaloric material must be subjected to. The magnet constitutes a major part of the expense of a complete magnetic refrigeration system and a large effort should therefore be invested in improving...... the magnet design. A detailed analysis of the efficiency of different published permanent magnet designs used in magnetic refrigeration applications is presented in this paper. Each design is analyzed based on the generated magnetic flux density, the volume of the region where this flux is generated...... and the amount of magnet material used. This is done by characterizing each design by a figure of merit magnet design efficiency parameter, Λcool. The designs are then compared and the best design found. Finally recommendations for designing the ideal magnet design are presented based on the analysis...

  5. 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).

  6. A Review of Research on Universal Design Educational Models

    Science.gov (United States)

    Rao, Kavita; Ok, Min Wook; Bryant, Brian R.

    2014-01-01

    Universal design for learning (UDL) has gained considerable attention in the field of special education, acclaimed for its promise to promote inclusion by supporting access to the general curriculum. In addition to UDL, there are two other universal design (UD) educational models referenced in the literature, universal design of instruction (UDI)…

  7. Demystifying Mixed Methods Research Design: A Review of the Literature

    Science.gov (United States)

    Caruth, Gail D.

    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.…

  8. 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.

  9. 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

  10. 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.

  11. 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.

  12. Advanced drug delivery systems: Nanotechnology of health design A review

    Directory of Open Access Journals (Sweden)

    Javad Safari

    2014-04-01

    Full Text Available Nanotechnology has finally and firmly entered the realm of drug delivery. Performances of intelligent drug delivery systems are continuously improved with the purpose to maximize therapeutic activity and to minimize undesirable side-effects. This review describes the advanced drug delivery systems based on micelles, polymeric nanoparticles, and dendrimers. Polymeric carbon nanotubes and many others demonstrate a broad variety of useful properties. This review emphasizes the main requirements for developing new nanotech-nology-based drug delivery systems.

  13. Empirical pillar design methods review report: Final report

    International Nuclear Information System (INIS)

    1988-02-01

    This report summarizes and evaluates empirical pillar design methods that may be of use during the conceptual design of a high-level nuclear waste repository in salt. The methods are discussed according to category (i.e, main, submain, and panel pillars; barrier pillars; and shaft pillars). Of the 21 identified for main, submain, and panel pillars, one method, the Confined Core Method, is evaluated as being most appropriate for conceptual design. Five methods are considered potentially applicable. Of six methods identified for barrier pillars, one method based on the Load Transfer Distance concept is considered most appropriate for design. Based on the evaluation of 25 methods identified for shaft pillars, an approximate sizing criterion is proposed for use in conceptual design. Aspects of pillar performance relating to creep, ground deformation, interaction with roof and floor rock, and response to high temperature environments are not adequately addressed by existing empirical design methods. 152 refs., 22 figs., 14 tabs

  14. 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

  15. 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

  16. 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.

  17. Organization Design for Dynamic Fit: A Review and Projection

    Directory of Open Access Journals (Sweden)

    Mark Nissen

    2014-08-01

    Full Text Available The concept of fit is central to organization design. In the organizational literature, fit historically has been portrayed as a static concept. Both organizations and their environments, however, are continually changing, so a valid concept of fit needs to reflect organizational dynamics. In this article, I analyze various theoretical perspectives and studies that relate to organizational fit, differentiating those that employ an equilibrating or a fluxing approach. Four substantive themes emerge from this analysis: design orientation, design tension, designer/manager roles, and measurement and validation. Implications of each of these themes for dynamic fit are derived, and promising future research directions are discussed.

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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

  7. 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

  8. 1L Mark-IV Target Design Review

    Energy Technology Data Exchange (ETDEWEB)

    Koehler, Paul E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-11-16

    This presentation includes General Design Considerations; Current (Mark-III) Lower Tier; Mark-III Upper Tier; Performance Metrics; General Improvements for Material Science; General Improvements for Nuclear Science; Improving FOM for Nuclear Science; General Design Considerations Summary; Design Optimization Studies; Expected Mark-IV Performance: Material Science; Expected Mark-IV Performance: Nuclear Science (Disk); Mark IV Enables Much Wider Range of Nuclear-Science FOM Gains than Mark III; Mark-IV Performance Summary; Rod or Disk? Center or Real FOV?; and Project Cost and Schedule.

  9. 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.

  10. Optical System Critical Design Review (CDR) Flight Software Summary

    Science.gov (United States)

    Khorrami, Mori

    2006-01-01

    The Mid Infrared Instrument (MIRI FSW presentation covers: (1) Optical System FSW only and Cooling System FSW is covered at its CDR (2) Requirements & Interfaces (3) Relationship with the ISIM FSW (4) FSW Design Drivers & Solutions.

  11. "Not for human consumption": a review of emerging designer drugs.

    Science.gov (United States)

    Musselman, Megan E; Hampton, Jeremy P

    2014-07-01

    Synthetic, or "designer" drugs, are created by manipulating the chemical structures of other psychoactive drugs so that the resulting product is structurally similar but not identical to illegal psychoactive drugs. Originally developed in the 1960s as a way to evade existing drug laws, the use of designer drugs has increased dramatically over the past few years. These drugs are deceptively packaged as "research chemicals," "incense," "bath salts," or "plant food," among other names, with labels that may contain warnings such as "not for human consumption" or "not for sale to minors." The clinical effects of most new designer drugs can be described as either hallucinogenic, stimulant, or opioid-like. They may also have a combination of these effects due to designer side-chain substitutions. The easy accessibility and rapid emergence of new designer drugs have created challenges for health care providers when treating patients presenting with acute toxicity from these substances, many of which can produce significant and/or life-threatening adverse effects. Moreover, the health care provider has no way to verify the contents and/or potency of the agent ingested because it can vary between packages and distributors. Therefore, a thorough knowledge of the available designer drugs, common signs and symptoms of toxicity associated with these agents, and potential effective treatment modalities are essential to appropriately manage these patients. © 2014 Pharmacotherapy Publications, Inc.

  12. 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…

  13. 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

  14. Review in Transverse Flux Permanent Magnet Generator Design

    Directory of Open Access Journals (Sweden)

    A. Ejlali

    2016-12-01

    Full Text Available Recently, Transverse Flux Permanent Magnet Generators (TFPMGs have been proposed as a possible generator in direct drive variable speed wind turbines due to their unique merits. Generally, the quality of output power in these systems is lower than multi stage fixed speed systems, because of removing the gears, so it’s important to design these kinds of generators with low ripple and lowest harmful harmonics and cogging torque that is one of the most important terms in increasing the quality of output power of generator. The objective of this paper is introducing a simple design method and optimization of high power TFPMG applied in vertical axis direct drive wind turbine system by lowest possible amplitude of cogging torque and highest possible power factor, efficiency and power density.  In order to extract the output values of generator and sensitivity analysis for design and optimization, 3D-Finite element model, has been used. This method has high accuracy and gives us a better insight of generator performance and presents back EMF, cogging torque, flux density and FFT of this TFPMG. This study can help designers in design approach of such motors.

  15. Function, Design, and Establishment of Riparian Forest Buffers: A Review

    OpenAIRE

    Klapproth, Julia Caldwell

    1999-01-01

    Through the interaction of their soils, hydrology, and biotic communities, riparian forests protect and improve water quality, provide habitat for plants and animals, support aquatic communities, and provide many benefits to humans. Virginia, along with other states in the Chesapeake Bay region, has recognized the importance of riparian forests by implementing a plan to restore forested buffers along streams, rivers, and lakes. This project reviews selected literature on riparian forest bu...

  16. 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.

  17. 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.

  18. The Optical Design of the Human Eye: a Critical Review

    Directory of Open Access Journals (Sweden)

    Rafael Navarro

    2009-01-01

    Full Text Available Cornea, lens and eye models are analyzed and compared to experimental findings to assess properties and eventually unveil optical design principles involved in the structure and function of the optical system of the eye. Models and data often show good match but also some paradoxes. The optical design seems to correspond to a wide angle lens. Compared to conventional optical systems, the eye presents a poor optical quality on axis, but a relatively good quality off-axis, thus yielding higher homogeneity for a wide visual field. This seems the result of an intriguing combination of the symmetry design principle with a total lack of rotational symmetry, decentrations and misalignments of the optical surfaces.

  19. Review of mixer design for low voltage - low power applications

    Science.gov (United States)

    Nurulain, D.; Musa, F. A. S.; Isa, M. Mohamad; Ahmad, N.; Kasjoo, S. R.

    2017-09-01

    A mixer is used in almost all radio frequency (RF) or microwave systems for frequency translation. Nowadays, the increase market demand encouraged the industry to deliver circuit designs to create proficient and convenient equipment with very low power (LP) consumption and low voltage (LV) supply in both digital and analogue circuits. This paper focused on different Complementary Metal Oxide Semiconductor (CMOS) design topologies for LV and LP mixer design. Floating Gate Metal Oxide Semiconductor (FGMOS) is an alternative technology to replace CMOS due to their high ability for LV and LP applications. FGMOS only required a few transistors per gate and can have a shift in threshold voltage (VTH) to increase the LP and LV performances as compared to CMOS, which makes an attractive option to replace CMOS.

  20. WAG (water-alternating-gas) process design: an update review

    Energy Technology Data Exchange (ETDEWEB)

    Zahoor, M.K. [University of Engineering and Technology, Lahore (Pakistan). Dept. of Petroleum and Gas Engineering], e-mail: mkzahoor@uet.edu.pk; Derahman, M.N.; Yunan, M.H. [Universiti Teknologi Malaysia, Johor (Malaysia). Dept. of Petroleum Engineering

    2011-04-15

    The design and implementation of water-alternating-gas (WAG) process in an improved and cost-effective way are still under process. Due to the complexities involved in implementing the process and the lack of information regarding fluid and reservoir properties, the water-alternating-gas process has not yet been as successful as initially expected. This situation can be overcome by better understanding the fluid distribution and flow behavior within the reservoir. The ultimate purpose can be achieved with improved knowledge on wettability and its influence on fluid distribution, capillary pressure, relative permeability, and other design parameters. This paper gives an insight on the WAG process design and the recently developed correlations which are helpful in incorporating the effects of wettability variations on fluid dynamics within the reservoir. (author)

  1. TPX: Contractor preliminary design review. Volume 2, PF systems engineering

    International Nuclear Information System (INIS)

    Calvin, H.A.

    1995-01-01

    This system development specification covers the Poloidal Field (PF) Magnet System, WBS 14 in the Princeton Plasma Physics Laboratory TPX Program to build a tokamak fusion reactor. This specification establishes the performance, design, development and test requirements of the PF Magnet System

  2. Review: Design parameters of rating scales for Web sites

    NARCIS (Netherlands)

    van den Broek, Egon

    2007-01-01

    With the increasing popularity of the Internet, more and more online questionnaires are being conducted. However, little research is being done on their construction, in particular on their design. The authors of this paper have conducted such a study, within the scope of rating scales for Web

  3. TPX: Contractor preliminary design review. Volume 2, PF systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Calvin, H.A. [Lawrence Livermore National Lab., CA (United States)

    1995-07-28

    This system development specification covers the Poloidal Field (PF) Magnet System, WBS 14 in the Princeton Plasma Physics Laboratory TPX Program to build a tokamak fusion reactor. This specification establishes the performance, design, development and test requirements of the PF Magnet System.

  4. 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

  5. Concise Review: Organ Engineering: Design, Technology, and Integration.

    Science.gov (United States)

    Kaushik, Gaurav; Leijten, Jeroen; Khademhosseini, Ali

    2017-01-01

    Engineering complex tissues and whole organs has the potential to dramatically impact translational medicine in several avenues. Organ engineering is a discipline that integrates biological knowledge of embryological development, anatomy, physiology, and cellular interactions with enabling technologies including biocompatible biomaterials and biofabrication platforms such as three-dimensional bioprinting. When engineering complex tissues and organs, core design principles must be taken into account, such as the structure-function relationship, biochemical signaling, mechanics, gradients, and spatial constraints. Technological advances in biomaterials, biofabrication, and biomedical imaging allow for in vitro control of these factors to recreate in vivo phenomena. Finally, organ engineering emerges as an integration of biological design and technical rigor. An overall workflow for organ engineering and guiding technology to advance biology as well as a perspective on necessary future iterations in the field is discussed. Stem Cells 2017;35:51-60. © 2016 AlphaMed Press.

  6. Design considerations and operational performance of Anaerobic Digester: A Review

    Directory of Open Access Journals (Sweden)

    Muzaffar Ahmad Mir

    2016-04-01

    Full Text Available Due to the decline in fossil fuel reservoirs, the researchers emphasized more on the production of biogas from organic waste. Producing the renewable energy from biodegradable waste helps to overcome the energy crisis and solid waste management, done by anaerobic digestion. Anaerobic digestion is controlled breakdown of organic matter into methane gas (60%, carbon dioxide (40%, trace components along with digested used as soil conditioner. However there is vast dearth of literature regarding the design considerations. The batch digestion system yields a cost-effective and economically viable means for conversion of the food waste to useful energy. It is therefore recommended that such process can be increasingly employed in order to get and simultaneously protect the environment .This paper aims to draw key analysis and concern about the design considerations, analysis of gas production, substrates and inoculums utilization, uses and impacts of biogas.

  7. Review of laser mega joule target area: Design and processes

    International Nuclear Information System (INIS)

    Geitzholz, M.; Lanternier, C.

    2006-01-01

    The Laser Mega Joule (LMJ) target area is currently designed to achieve ignition and significant fusion gain in laboratory. LMJ will be composed of 240 identical large 370 mm * 370 mm square laser beams. These beams will focus 2 mega-joules of energy at the wavelength of 351 nm on the center of an experiment chamber. Design studies for target equipment are well advanced, target chamber and target holder (concrete) works have already begun. A detailed overview of the target area equipment is presented: target chamber, frame, diagnostic inserter manipulator, final optic assembly, dual diagnostic and laser reference, non cryogenic target positioner. Recent technical and architectural choices are detailed including safety transfers and alignment processes (target, laser and diagnostic). All this target equipment allows us to optimize shot chrono-gram, from target metrology to the shot, including calibration process. (authors)

  8. The Mixed Waste Management Facility. Preliminary design review

    International Nuclear Information System (INIS)

    1995-01-01

    This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones

  9. REVIEW KONSEP RESPONSIVE DESIGN DENGAN FRAMEWORK MATERIALIZE PADA WEBSITE

    OpenAIRE

    Cindy Novianty

    2017-01-01

    Responsive web design merupakan sebuah desain website yang dapat menyesuaikan tiap ukuran pada tiap device. Berdasarkan hasil dari beberapa responden menyatakan 62% responden setuju jika beberapa website yang belum mampu menyesuaikan ukuran tampilan web, 54% responden setuju bahwa desain yang responsive mempengaruhi faktor kenyamanan responden, 60% responden setuju bahwa konten utama dan fungsionalitas dari website yang sulit diakses melalui perangkat mobile, 56% responden setuju bahwa tampil...

  10. 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.

  11. 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.

  12. Strategic Ozone Sounding Networks: Review of Design and Accomplishments

    Science.gov (United States)

    Thompson, Anne M.; Oltmans, Samuel J.; Tarasick, David W.; von der Gathen, Peter; Smit, Herman G. J.; Witte, Jacquelyn C.

    2011-01-01

    Ozone soundings are used to integrate models, satellite, aircraft and ground-based measurements for better interpretation of ozone variability, including atmospheric losses (predominantly in the stratosphere) and pollution (troposphere). A well-designed network of ozonesonde stations gives information with high vertical and horizontal resolution on a number of dynamical and chemical processes, allowing us to answer questions not possible with aircraft campaigns or current satellite technology. Strategic ozonesonde networks are discussed for high, mid- and low latitude studies. The Match sounding network was designed specifically to follow ozone depletion within the polar vortex; the standard sites are at middle to high northern hemisphere latitudes and typically operate from December through mid-March. Three mid-latitude strategic networks (the IONS series) operated over North America in July-August 2004, March-May and August 2006, and April and June-July-2008. These were designed to address questions about tropospheric ozone budgets and sources, including stratosphere-troposphere transport, and to validate satellite instruments and models. A global network focusing on processes in the equatorial zone, SHADOZ (Southern Hemisphere Additional Ozonesondes), has operated since 1998 in partnership with NOAA, NASA and the Meteorological Services of host countries. Examples of important findings from these networks are described,

  13. Design and operation of nitrifying trickling filters in recirculating aquaculture: a review

    NARCIS (Netherlands)

    Eding, E.H.; Kamstra, A.; Verreth, J.A.J.; Huisman, E.A.; Klapwijk, A.

    2006-01-01

    This review deals with the main mechanisms and parameters affecting design and performance of trickling filters in aquaculture. Relationships between nitrification rates and easily accessible process parameters, like bulk phase concentration of TAN, O2, organic matter (COD), nitrite, temperature,

  14. 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

  15. Review and future perspective of central receiver design and performance

    Science.gov (United States)

    Zhu, Guangdong; Libby, Cara

    2017-06-01

    Concentrating solar power (CSP) technology provides a commercial solar option to the utility-scale electricity market. CSP is unique in its ability to include low-cost thermal storage; thus, it can generate electricity when the sun is not available and dispatch electricity to meet varying load requirements. Within the suite of CSP technologies, the central receiver design represents the state-of-the-art technology, promising low cost, high performance, and dispatchable energy production. Current total capacity of central receiver plants worldwide is about 1.0 gigawatt (electric) with operating plants in Spain and the United States, as well as projects under construction in Asia, the Middle East, and North Africa. Central receiver technology has been under development since the 1950s, and a variety of central receiver designs have been explored. A distinguishing feature is the heat transfer medium. Central receiver designs exist that use dense fluids, gases, and solid particles in this role. Water/steam and molten salt receivers have been adopted in current commercial plants and are often coupled with a steam-Rankine power cycle with an operating temperature of less than 600°C. Many new central receiver concepts, such as the volumetric air, supercritical carbon dioxide (sCO2), solid particle, and liquid-metal receiver designs, are under active research and development (R&D). New designs target operating temperatures generally higher than 700°C-800°C—and even above 1000°C—so that higher-performance power cycles such as the sCO2-Brayton cycle or air-Brayton/steam-Rankine combined cycle can be used to promote greater overall system efficiency. Central receiver thermal storage provides dispatchability unavailable from variable-output renewables such as solar photovoltaic and wind power. Case study analysis of the California grid shows that there is a limit on the amount of non-dispatchable renewable generation that the grid can accommodate, beyond which

  16. Review and Future Perspective of Central Receiver Design and Performance

    Energy Technology Data Exchange (ETDEWEB)

    Zhu, Guangdong; Libby, Cara

    2017-06-27

    Concentrating solar power (CSP) technology provides a commercial solar option to the utility-scale electricity market. CSP is unique in its ability to include low-cost thermal storage; thus, it can generate electricity when the sun is not available and dispatch electricity to meet varying load requirements. Within the suite of CSP technologies, the central receiver design represents the state-of-the-art technology, promising low cost, high performance, and dispatchable energy production. Current total capacity of central receiver plants worldwide is about 1.0 gigawatt (electric) with operating plants in Spain and the United States, as well as projects under construction in Asia, the Middle East, and North Africa. Central receiver technology has been under development since the 1950s, and a variety of central receiver designs have been explored. A distinguishing feature is the heat transfer medium. Central receiver designs exist that use dense fluids, gases, and solid particles in this role. Water/steam and molten salt receivers have been adopted in current commercial plants and are often coupled with a steam-Rankine power cycle with an operating temperature of less than 600 degrees C. Many new central receiver concepts, such as the volumetric air, supercritical carbon dioxide (sCO2), solid particle, and liquid-metal receiver designs, are under active research and development (R&D). New designs target operating temperatures generally higher than 700 degrees C-800 degrees C -- and even above 1000 degrees C -- so that higher-performance power cycles such as the sCO2-Brayton cycle or air-Brayton/steam-Rankine combined cycle can be used to promote greater overall system efficiency. Central receiver thermal storage provides dispatchability unavailable from variable-output renewables such as solar photovoltaic and wind power. Case study analysis of the California grid shows that there is a limit on the amount of non-dispatchable renewable generation that the grid can

  17. 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

  18. 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

  19. Hydrothermal Carbonization: Modeling, Final Properties Design and Applications: A Review

    Directory of Open Access Journals (Sweden)

    Silvia Román

    2018-01-01

    Full Text Available Active research on biomass hydrothermal carbonization (HTC continues to demonstrate its advantages over other thermochemical processes, in particular the interesting benefits that are associated with carbonaceous solid products, called hydrochar (HC. The areas of applications of HC range from biofuel to doped porous material for adsorption, energy storage, and catalysis. At the same time, intensive research has been aimed at better elucidating the process mechanisms and kinetics, and how the experimental variables (temperature, time, biomass load, feedstock composition, as well as their interactions affect the distribution between phases and their composition. This review provides an analysis of the state of the art on HTC, mainly with regard to the effect of variables on the process, the associated kinetics, and the characteristics of the solid phase (HC, as well as some of the more studied applications so far. The focus is on research made over the last five years on these topics.

  20. A review on electrospinning design and nanofibre assemblies

    International Nuclear Information System (INIS)

    Teo, W E; Ramakrishna, S

    2006-01-01

    Although there are many methods of fabricating nanofibres, electrospinning is perhaps the most versatile process. Materials such as polymer, composites, ceramic and metal nanofibres have been fabricated using electrospinning directly or through post-spinning processes. However, what makes electrospinning different from other nanofibre fabrication processes is its ability to form various fibre assemblies. This will certainly enhance the performance of products made from nanofibres and allow application specific modifications. It is therefore vital for us to understand the various parameters and processes that allow us to fabricate the desired fibre assemblies. Fibre assemblies that can be fabricated include nonwoven fibre mesh, aligned fibre mesh, patterned fibre mesh, random three-dimensional structures and sub-micron spring and convoluted fibres. Nevertheless, more studies are required to understand and precisely control the actual mechanics in the formation of various electrospun fibrous assemblies. (topical review)

  1. Credibility judgments in web page design - a brief review.

    Science.gov (United States)

    Selejan, O; Muresanu, D F; Popa, L; Muresanu-Oloeriu, I; Iudean, D; Buzoianu, A; Suciu, S

    2016-01-01

    Today, more than ever, knowledge that interfaces appearance analysis is a crucial point in human-computer interaction field has been accepted. As nowadays virtually anyone can publish information on the web, the credibility role has grown increasingly important in relation to the web-based content. Areas like trust, credibility, and behavior, doubled by overall impression and user expectation are today in the spotlight of research compared to the last period, when other pragmatic areas such as usability and utility were considered. Credibility has been discussed as a theoretical construct in the field of communication in the past decades and revealed that people tend to evaluate the credibility of communication primarily by the communicator's expertise. Other factors involved in the content communication process are trustworthiness and dynamism as well as various other criteria but to a lower extent. In this brief review, factors like web page aesthetics, browsing experiences and user experience are considered.

  2. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement. Refs, figs, tabs

  3. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    International Nuclear Information System (INIS)

    1998-01-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement

  4. LHCb Upgraded RICH 2 Engineering Design Review Report

    CERN Document Server

    Garsed, Philip John; Cardinale, Roberta; Petrolini, Alessandro; Benettoni, Massimo; Simi, Gabriele; Zago, M; Easo, Sajan; D'Ambrosio, Carmelo; Frei, Christoph; He, Jibo; Piedigrossi, Didier

    2016-01-01

    During the Long Shutdown 2 of the LHC, the LHCb experiment and, specifically, its two Ring Imaging Cherenkov (RICH) detectors will undergo a major upgrade. RICH 2 will be refurbished with new photon detectors and their associated electronics, with the capability of up to 40 MHz sustained acquisition rate. A new support and cooling system has been developed for the two photodetector arrays, retaining the vessel, gas and optical systems unchanged. This document describes their new mechanical arrangement, its engineering design, installation and alignment. A summary of the project schedule and Institute responsibilities is provided.

  5. The State of Design : A Comprehensive Literature Review to Chart the Design Science Research Discourse

    NARCIS (Netherlands)

    Thakurta, Rahul; Mueller, Benjamin; Ahlemann, Frederik; Hoffman, David

    Design science is an increasingly popular research paradigm in the information systems discipline. De- spite a recognition of the design science research par- adigm, questions are being raised about the nature of its existence and its contributions. Central to this ar- gument is the understanding of

  6. 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

  7. A review of the core catcher design in LMR

    International Nuclear Information System (INIS)

    Lee, Yong Bum; Hahn, Do Hee

    2001-08-01

    The overwhelming emphasis in reactor safety is on the prevention of core meltdown. Moreover, although there have been several accidents that have resulted in some fuel melting, to date there have been no accidents severe enough to cause the syndrome of core collapse, reactor vessel melt-through, containment penetration, and dispersal into the ground. Nevertheless, a number of proposals have been made for the design of core catcher systems to control or stop the motion of the molten core mass should such an accident take place. Core catchers may differ in both their location within the reactor system and in the mechanism that is used to cool and control the motion of the core debris. In this report the classification, configuration and main features of the core catcher are described. And also, The core catcher design technologies and processes are presented. Finally the core catcher provisions in constructed and planned LMRs (Liquid Metal Reactors) are summarized and the preliminary assessment on the core catcher installation in KALIMER is presented

  8. 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)

  9. A Review of Research Methods in Children's Technology Design

    DEFF Research Database (Denmark)

    Jensen, Janne Jul; Skov, Mikael B.

    2005-01-01

    Research methods have been objects of discussions for dec-ades and defining research methods is still a quite substan-tial challenge. However, it is important to understand how research methods have been adapted in different disciplines as it potentially informs us on future directions and influ......-ences on the discipline. Inspired by previous studies from other disciplines, we conduct a survey of research methods in paper publications. 105 papers on children's technology design are classified on a two-dimensional matrix on research method and pur-pose. Our results show a strong focus on engineering of products...... as applied research and on evaluation of devel-oped products in the field or in the lab. Also, we find that much research is conducted in natural setting environments with strong focus on field studies....

  10. 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

  11. 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.

  12. 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…

  13. 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.

  14. 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

  15. User Experience Design of History Game: An Analysis Review and Evaluation Study for Malaysia Context

    Science.gov (United States)

    Wong, Seng Yue; Ghavifekr, Simin

    2018-01-01

    User experience (UX) and user interface design of an educational game are important in enhancing and sustaining the utilisation of Game Based Learning (GBL) in learning history. Thus, this article provides a detailed literature review on history learning problems, as well as previous studies on user experience in game design. Future studies on…

  16. 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.

  17. Wolsong 2, 3, and 4 quarterly progress review report on NSSS design and engineering

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Sung Hoon; Kim, Sun Kee; Park, Tae Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-01-01

    This is the Quarterly Progress Review Report for Wolsong NPP 2, 3 and 4 NSSS Design and Engineering which evaluates the performance of the project and describes the project highlight, manpower loading status, design and engineering and project related meetings by quarterly basis. 29 figs., 16 tabs. (Author).

  18. 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)

  19. GIS tools for analyzing accidents and road design: A review

    Energy Technology Data Exchange (ETDEWEB)

    Satria, R.

    2016-07-01

    A significant unexpected outcome of transportation systems is road accidents with injuries and loss of lives. In recent years, the number of studies about the tools for analyzing accidents and road design has increased considerably. Among these tools, Geographical Information Systems (GIS) stand out for their ability to perform complex spatial analyses. However, sometimes the GIS, has been used only as a geographical database to store and represent data about accidents and road characteristics. It has also been used to represent the results of statistical studies of accidents but, these statistical studies have not been carried out with GIS. Owing to its integrated statistical-analysis capabilities GIS provides several advantages. First, it allows a more careful and accurate data selection, screening and reduction. Also, it allows a spatial analysis of the results in pre and post-processing. Second, GIS allows the development of spatial statistics that rely on geographically-referenced data. In this paper, several GIS tools used to model accidents have been examined. The understanding of these tools will help the analyst to make a better decision about which tool could be applied in each particular condition and context. (Author)

  20. 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.

  1. 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

  2. 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

  3. 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

  4. The NASA Monographs on Shell Stability Design Recommendations: A Review and Suggested Improvements

    Science.gov (United States)

    Nemeth, Michael P.; Starnes, James H., Jr.

    1998-01-01

    A summary of the existing NASA design criteria monographs for the design of buckling-resistant thin-shell structures is presented. Subsequent improvements in the analysis for nonlinear shell response are reviewed, and current issues in shell stability analysis are discussed. Examples of nonlinear shell responses that are not included in the existing shell design monographs are presented, and an approach for including reliability-based analysis procedures in the shell design process is discussed. Suggestions for conducting future shell experiments are presented, and proposed improvements to the NASA shell design criteria monographs are discussed.

  5. Technical basis for the ITER detailed design report, cost review and safety analysis (DDR)

    International Nuclear Information System (INIS)

    1997-01-01

    The ITER Detailed Design Report (DDR), Cost Review and Safety Analysis is the 3rd major milestone representing the progress made in the ITER Engineering Design Activities. With the approval of the Interim Design Report (IDR), it has been possible to freeze the main concepts and system approaches for ITER and to develop the design in more detail for the individual components and sub-systems. This report, although designed to be fully understandable as a separate document, focusses particularly on the main changes since the IDR

  6. Technical basis for the ITER detailed design report, cost review and safety analysis (DDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The ITER Detailed Design Report (DDR), Cost Review and Safety Analysis is the 3rd major milestone representing the progress made in the ITER Engineering Design Activities. With the approval of the Interim Design Report (IDR), it has been possible to freeze the main concepts and system approaches for ITER and to develop the design in more detail for the individual components and sub-systems. This report, although designed to be fully understandable as a separate document, focusses particularly on the main changes since the IDR. Refs, figs, tabs

  7. Using Vector Projection Method to evaluate maintainability of mechanical system in design review

    International Nuclear Information System (INIS)

    Chen Lu; Cai Jianguo

    2003-01-01

    Maintainability of a mechanical system is one of the system design parameters that has a great impact in terms of ease of maintenance. In this article, based on the definition of the terms of maintenance and maintainability, an important tool of Design for Maintenance is developed as a way to improve maintainability through design. A set of standard and organized guidelines is provided and maintainability factors in terms of physical design, logistics support and ergonomics are identified. As a specific application of design review, a methodology so called Vector Projection Method is developed to evaluate the maintainability of the mechanical system. Lastly, an example is discussed

  8. Ergonomic (human factors) problems in design of NPPs. A review of TMI and Chernobyl accidents

    International Nuclear Information System (INIS)

    Huang Xiangrui; Zheng Fuyu; Gao Jia

    1994-01-01

    The general principle of ergonomic in design of NPPs is given and some causes of TMI and Chernobyl accidents from the view point of human factor engineering are reviewed. The paper also introduces some Ergonomic problems in design, operation and management of earlier NPPs. Some ergonomic principles of man-machine systems design have been described. Some proposals have been suggested for improving human reliability in NPPs

  9. Review: Janice M. Morse & Linda Niehaus (2009). Mixed Method Design: Principles and Procedures

    OpenAIRE

    Öhlen, Joakim

    2010-01-01

    Mixed method design related to the use of a combination of methods, usually quantitative and qualitative, is increasingly used for the investigation of complex phenomena. This review discusses the book, "Mixed Method Design: Principles and Procedures," by Janice M. MORSE and Linda NIEHAUS. A distinctive feature of their approach is the consideration of mixed methods design out of a core and a supplemental component. In order to define these components they emphasize the overall conceptual dir...

  10. 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

  11. 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.

  12. Engineered design features in the HI-STAR/HI-STORM systems to maximize ALARA, safety, and community acceptance

    International Nuclear Information System (INIS)

    Blessing, Christian

    2003-01-01

    Heltec International is a U.S. corporation headquartered in New Jersey, dedicated to providing capital goods and technical services to the power industry. Over 75 percent of the company's product output is destined for nuclear power plants. Holter counts among its active clients a majority of the nuclear plants in the United States, as well as Korea, Taiwan, Mexico, and Brazil. The company also has a growing market presence in Japan and the European Union. Leading U.S. nuclear plant owners, such as Entergy, Exelon, FPL, Southern Nuclear, PG and E and TVA have a long-term and continuous business relationship with Holtec International. This article deals with Holtec dry storage system description, the multi-purpose canister, hi-star 100 overpack, hi-storm 100 overpack and unique advantages of holtec's dry storage technology

  13. 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

  14. A REVIEW: A MODEL of CULTURAL ASPECTS for SUSTAINABLE PRODUCT DESIGN

    Directory of Open Access Journals (Sweden)

    Ihwan Ghazali,

    2012-04-01

    Full Text Available Product design stages are important to consider critically in production. Generally, product design that shall be created by designer, should consider what the customer wants and needs. Nowadays issues, product design does not only consider the “wants and needs” of user, but also how the design can be created by embedding sustainability aspects in the product. Culture is also one of the important aspects which need to be considered in product design as culture affects the way users respond to the product. This paper aims to develop a new model for design development, in which the aspects of culture are incorporated into sustainable product design. By reviewing the existing literature, the authors attempt to identify the gaps of the existing papers, which illustrate how culture affects sustainable product design. Recent papers have only shown that culture influences product design, but they do not explore sustainability and the culture aspects in product design. Due to these gaps, it is therefore important to create a model which will assist designers to elicit sustainable product design based on cultural aspects. In summary, designers need to reflect on the “wants and needs” of users. The framework presented in this paper can be integrated into designers’ and companies’ decision-making during product design development.

  15. Committee Report of the BEPC-II Project Design Review May 13-15, 2002, SLAC

    Energy Technology Data Exchange (ETDEWEB)

    Kawakami, Traci M.

    2002-08-26

    As part of the US-China Cooperative Program in High Energy Physics for the year 2002, a BEPC-II Upgrade Review meeting was held at SLAC, May 13-15, 2002. The upgrade is aimed at improving the luminosity and performance of the BEPC facility at IHEP in Beijing, China with major upgrades to the injector linac, storage ring, and detector. This review addresses mainly the accelerator related issues. Prior to the review, an updated Draft Design Report was made available to the review team. Most important technical change since April 2001 has been a change from a single-ring configuration to a doublering. The goal of the review is to determine whether BEPC-II, if built as described, will meet the operations and physics goals. The charge to the review team is attached as Appendix A.

  16. TPX: Contractor preliminary design review. Volume 1, Presentation and design description. Final report

    International Nuclear Information System (INIS)

    Hartman, D.; Naumovich; Walstrom, P.; Clarkson, I.; Schultheiss, J.; Burger, A.

    1995-01-01

    This first volume of the five volume set begins with a CPDR overview and then details the PF magnet system, manufacturing R ampersand D, Westinghouse R ampersand D, the central solenoid, the PF 5 ring coil, the PF 6/7 ring coil, quality assurance, and the system design description

  17. Interventions designed to reduce sedentary behaviours in young people: a review of reviews.

    Science.gov (United States)

    Biddle, Stuart J H; Petrolini, Irene; Pearson, Natalie

    2014-02-01

    Leisure time is increasingly spent in sedentary pursuits such as screen-viewing (eg, television/DVD viewing and computer use), motorised travel, school/work and sitting-based socialising (eg, social media and chatting). Sedentary screen time, particularly TV, appears to play an important role in the aetiology of obesity due to its co-occurrence with other unhealthy behaviours such as snacking on energy-dense foods, low levels of physical activity and inadequate sleep. More information is needed on how to reduce sedentary behaviours. Most interventions have focused on young people and a number of systematic reviews exist on this topic. To synthesise systematic reviews and meta-analyses of interventions aimed at decreasing sedentary behaviours among children and adolescents. Papers were located from computerised and manual searches. Included articles were English language systematic reviews or meta-analyses of interventions aiming at reducing sedentary behaviour in children (<11 years) and adolescents (12-18 years). Ten papers met the inclusion criteria and were analysed. All reviews concluded some level of effectiveness in reducing time spent in sedentary behaviour. When an effect size was reported, there was a small but significant reduction in sedentary time (highest effect size=-0.29; CI -0.35 to -0.22). Moderator analyses showed a trend favouring interventions with children younger than 6 years. Effective strategies include the involvement of family, behavioural interventions and electronic TV monitoring devices. Results from systematic reviews and meta-analyses show that interventions to reduce children's sedentary behaviour have a small but significant effect. Future research should expand these findings examining interventions targeting different types of sedentary behaviours and the effectiveness of specific behaviour change techniques across different contexts and settings.

  18. Toward best practice in Human Machine Interface design for older drivers: A review of current design guidelines.

    Science.gov (United States)

    Young, K L; Koppel, S; Charlton, J L

    2017-09-01

    Older adults are the fastest growing segment of the driving population. While there is a strong emphasis for older people to maintain their mobility, the safety of older drivers is a serious community concern. Frailty and declines in a range of age-related sensory, cognitive, and physical impairments can place older drivers at an increased risk of crash-related injuries and death. A number of studies have indicated that in-vehicle technologies such as Advanced Driver Assistance Systems (ADAS) and In-Vehicle Information Systems (IVIS) may provide assistance to older drivers. However, these technologies will only benefit older drivers if their design is congruent with the complex needs and diverse abilities of this driving cohort. The design of ADAS and IVIS is largely informed by automotive Human Machine Interface (HMI) guidelines. However, it is unclear to what extent the declining sensory, cognitive and physical capabilities of older drivers are addressed in the current guidelines. This paper provides a review of key current design guidelines for IVIS and ADAS with respect to the extent they address age-related changes in functional capacities. The review revealed that most of the HMI guidelines do not address design issues related to older driver impairments. In fact, in many guidelines driver age and sensory cognitive and physical impairments are not mentioned at all and where reference is made, it is typically very broad. Prescriptive advice on how to actually design a system so that it addresses the needs and limitations of older drivers is not provided. In order for older drivers to reap the full benefits that in-vehicle technology can afford, it is critical that further work establish how older driver limitations and capabilities can be supported by the system design process, including their inclusion into HMI design guidelines. Copyright © 2016 Elsevier Ltd. All rights reserved.

  19. Reviews.

    Science.gov (United States)

    Journal of Chemical Education, 1987

    1987-01-01

    Provides a review of both the Apple and IBM versions of ENZPACK, a software package which is designed to assist in the teaching of enzyme kinetics in courses where this topic is treated in some depth. (TW)

  20. 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.

  1. WIPP conceptual design report. Addendum L. Mine safety code review for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1977-06-01

    An initial review of New Mexico and Federal mining standards and regulations has been made to determine their applicability to the WIPP conceptual design. These standards and regulations are reviewed point by point and the enclosed listing includes comments and recommendations for those which will affect the design and/or eventual operations of WIPP. The majority of the standards, both federal and state, are standard safe mining practices. Those standards are listed which are thought should be emphasized for development of the design; also those that would increase the hazard risk by strict compliance. Because the WIPP facility is different in many respects from mines for which the regulations were intended, strict compliance in some respects would provide an increased hazard, while in other instances the regulations are less strict than is desirable. These are noted in the attached review

  2. 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

  3. Review of design approaches of advanced pressurized LWRs. Report of a technical committee meeting and workshop

    International Nuclear Information System (INIS)

    1996-01-01

    The Technical Committee Meeting and Workshop was devoted to review and discuss differences and commonalties in the various design approaches with the aim of increasing the understanding of the design decisions taken, and a number of general conclusions were drawn. Though many differences in design approaches were found in the presentations, a number of common features could also be identified. These included design approaches to achieve further improvements with respect to safety, design simplification, reduction in cost, incorporation of feedback from operating experience, and control room improvements regarding human factors and digitization. Design approaches to achieve further improvements in safety included consideration of severe accidents in the design process, increased thermal margins and water inventories, longer grace periods and double containments. Refs, figs and tabs

  4. 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

  5. Review of design approaches of advanced pressurized LWRs. Report of a technical committee meeting and workshop

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Technical Committee Meeting and Workshop was devoted to review and discuss differences and commonalties in the various design approaches with the aim of increasing the understanding of the design decisions taken, and a number of general conclusions were drawn. Though many differences in design approaches were found in the presentations, a number of common features could also be identified. These included design approaches to achieve further improvements with respect to safety, design simplification, reduction in cost, incorporation of feedback from operating experience, and control room improvements regarding human factors and digitization. Design approaches to achieve further improvements in safety included consideration of severe accidents in the design process, increased thermal margins and water inventories, longer grace periods and double containments. Refs, figs and tabs.

  6. 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

  7. 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

  8. Variation in Research Designs Used to Test the Effectiveness of Dissemination and Implementation Strategies: A Review.

    Science.gov (United States)

    Mazzucca, Stephanie; Tabak, Rachel G; Pilar, Meagan; Ramsey, Alex T; Baumann, Ana A; Kryzer, Emily; Lewis, Ericka M; Padek, Margaret; Powell, Byron J; Brownson, Ross C

    2018-01-01

    The need for optimal study designs in dissemination and implementation (D&I) research is increasingly recognized. Despite the wide range of study designs available for D&I research, we lack understanding of the types of designs and methodologies that are routinely used in the field. This review assesses the designs and methodologies in recently proposed D&I studies and provides resources to guide design decisions. We reviewed 404 study protocols published in the journal Implementation Science from 2/2006 to 9/2017. Eligible studies tested the efficacy or effectiveness of D&I strategies (i.e., not effectiveness of the underlying clinical or public health intervention); had a comparison by group and/or time; and used ≥1 quantitative measure. Several design elements were extracted: design category (e.g., randomized); design type [e.g., cluster randomized controlled trial (RCT)]; data type (e.g., quantitative); D&I theoretical framework; levels of treatment assignment, intervention, and measurement; and country in which the research was conducted. Each protocol was double-coded, and discrepancies were resolved through discussion. Of the 404 protocols reviewed, 212 (52%) studies tested one or more implementation strategy across 208 manuscripts, therefore meeting inclusion criteria. Of the included studies, 77% utilized randomized designs, primarily cluster RCTs. The use of alternative designs (e.g., stepped wedge) increased over time. Fewer studies were quasi-experimental (17%) or observational (6%). Many study design categories (e.g., controlled pre-post, matched pair cluster design) were represented by only one or two studies. Most articles proposed quantitative and qualitative methods (61%), with the remaining 39% proposing only quantitative. Half of protocols (52%) reported using a theoretical framework to guide the study. The four most frequently reported frameworks were Consolidated Framework for Implementing Research and RE-AIM ( n  = 16 each), followed by

  9. Variation in Research Designs Used to Test the Effectiveness of Dissemination and Implementation Strategies: A Review

    Directory of Open Access Journals (Sweden)

    Stephanie Mazzucca

    2018-02-01

    Full Text Available BackgroundThe need for optimal study designs in dissemination and implementation (D&I research is increasingly recognized. Despite the wide range of study designs available for D&I research, we lack understanding of the types of designs and methodologies that are routinely used in the field. This review assesses the designs and methodologies in recently proposed D&I studies and provides resources to guide design decisions.MethodsWe reviewed 404 study protocols published in the journal Implementation Science from 2/2006 to 9/2017. Eligible studies tested the efficacy or effectiveness of D&I strategies (i.e., not effectiveness of the underlying clinical or public health intervention; had a comparison by group and/or time; and used ≥1 quantitative measure. Several design elements were extracted: design category (e.g., randomized; design type [e.g., cluster randomized controlled trial (RCT]; data type (e.g., quantitative; D&I theoretical framework; levels of treatment assignment, intervention, and measurement; and country in which the research was conducted. Each protocol was double-coded, and discrepancies were resolved through discussion.ResultsOf the 404 protocols reviewed, 212 (52% studies tested one or more implementation strategy across 208 manuscripts, therefore meeting inclusion criteria. Of the included studies, 77% utilized randomized designs, primarily cluster RCTs. The use of alternative designs (e.g., stepped wedge increased over time. Fewer studies were quasi-experimental (17% or observational (6%. Many study design categories (e.g., controlled pre–post, matched pair cluster design were represented by only one or two studies. Most articles proposed quantitative and qualitative methods (61%, with the remaining 39% proposing only quantitative. Half of protocols (52% reported using a theoretical framework to guide the study. The four most frequently reported frameworks were Consolidated Framework for Implementing Research and RE

  10. 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...

  11. A REVIEW OF OIL PALM BIOCOMPOSITES FOR FURNITURE DESIGN AND APPLICATIONS: POTENTIAL AND CHALLENGES

    OpenAIRE

    Siti Suhaily,; Mohammad Jawaid,; H. P. S. Abdul Khalil,; A. Rahman Mohamed; , F. Ibrahim

    2012-01-01

    This review considers the potential and challenges of using agro-based oil palm biomasses, including the trunk, frond, empty fruit bunch, and palm press fiber biocomposites, for furniture applications. Currently, design and quality rather than price are becoming the primary concern for consumers when buying new furniture. Within this context, this paper focuses on the design of innovative, sustainable furniture from agro-based biocomposites to meet the needs of future population growth and te...

  12. Designing Patient-facing Health Information Technologies for the Outpatient Settings: A Literature Review

    OpenAIRE

    Yushi Yang; Onur Asan

    2016-01-01

    Introduction: The implementation of health information technologies (HITs) has changed the dynamics of doctor–patient communication in outpatient settings. Designing patient-facing HITs provides patients with easy access to healthcare information during the visit and has the potential to enhance the patient-centred care.   Objectives: The objectives of this study are to systematically review how the designs of patient-facing HITs have been suggested and evaluated, and how they may pot...

  13. Work boot design affects the way workers walk: A systematic review of the literature.

    Science.gov (United States)

    Dobson, Jessica A; Riddiford-Harland, Diane L; Bell, Alison F; Steele, Julie R

    2017-05-01

    Safety boots are compulsory in many occupations to protect the feet of workers from undesirable external stimuli, particularly in harsh work environments. The unique environmental conditions and varying tasks performed in different occupations necessitate a variety of boot designs to match each worker's occupational safety and functional requirements. Unfortunately, safety boots are often designed more for occupational safety at the expense of functionality and comfort. In fact, there is a paucity of published research investigating the influence that specific variations in work boot design have on fundamental tasks common to many occupations, such as walking. This literature review aimed to collate and examine what is currently known about the influence of boot design on walking in order to identify gaps in the literature and develop evidence-based recommendations upon which to design future research studies investigating work boot design. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. 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.

  15. 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.

  16. Groundwater Energy Designer - Review of basic data and modification; Grundlagendatenueberpruefung und Anpassungen des Groundwater Energy Designer (Teilprojekt Programmoptimierung) - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Poppei, J.; Mayer, G.; Schwarz, R.

    2009-12-15

    This report for the Swiss Federal Office of Energy (SFOE) reports on the extension and improvement of the Groundwater Energy Designer programme. A survey of selected existing small and medium sized ground-water heat pump systems formed the basis of the review. In this first phase of the project, a concept for measurement technologies to be used and the software changes necessary are discussed. The changes to the existing programme library to enable operation under Windows Vista, Windows 7 and Mac OSX are discussed. Also user dialogues were revised. New features and changes are presented and discussed, as are the functionality and user interface of the new version.

  17. Applying Quality Indicators to Single-Case Research Designs Used in Special Education: A Systematic Review

    Science.gov (United States)

    Moeller, Jeremy D.; Dattilo, John; Rusch, Frank

    2015-01-01

    This study examined how specific guidelines and heuristics have been used to identify methodological rigor associated with single-case research designs based on quality indicators developed by Horner et al. Specifically, this article describes how literature reviews have applied Horner et al.'s quality indicators and evidence-based criteria.…

  18. 78 FR 66972 - Submission for Review: Designation of Beneficiary: Civil Service Retirement System (CSRS), SF 2808

    Science.gov (United States)

    2013-11-07

    ... OFFICE OF PERSONNEL MANAGEMENT Submission for Review: Designation of Beneficiary: Civil Service Retirement System (CSRS), SF 2808 AGENCY: U.S. Office of Personnel Management. ACTION: 60-Day notice and... Retirement System, SF 2808. As required by the Paperwork Reduction Act of 1995 (Pub. L. 104-13, 44 U.S.C...

  19. 4MOST: the 4-metre Multi-Object Spectroscopic Telescope project at preliminary design review

    NARCIS (Netherlands)

    de Jong, Roelof S.; Barden, Samuel C.; Bellido-Tirado, Olga; Brynnel, Joar G.; Frey, Steffen; Giannone, Domenico; Haynes, Roger; Johl, Diana; Phillips, Daniel; Schnurr, Olivier; Walcher, Jakob C.; Winkler, Roland; Ansorge, Wolfgang R.; Feltzing, Sofia; McMahon, Richard G.; Baker, Gabriella; Caillier, Patrick; Dwelly, Tom; Gaessler, Wolfgang; Iwert, Olaf; Mandel, Holger G.; Piskunov, Nikolai A.; Pragt, Johan H.; Walton, Nicholas A.; Bensby, Thomas; Bergemann, Maria; Chiappini, Cristina; Christlieb, Norbert; Cioni, Maria-Rosa L.; Driver, Simon; Finoguenov, Alexis; Helmi, Amina; Irwin, Michael J.; Kitaura, Francisco-Shu; Kneib, Jean-Paul; Liske, Jochen; Merloni, Andrea; Minchev, Ivan; Richard, Johan; Starkenburg, Else

    2016-01-01

    We present an overview of the 4MOST project at the Preliminary Design Review. 4MOST is a major new wide-field, high-multiplex spectroscopic survey facility under development for the VISTA telescope of ESO. 4MOST has a broad range of science goals ranging from Galactic Archaeology and stellar physics

  20. The Usefulness of Systematic Reviews of Animal Experiments for the Design of Preclinical and Clinical Studies

    Science.gov (United States)

    de Vries, Rob B. M.; Wever, Kimberley E.; Avey, Marc T.; Stephens, Martin L.; Sena, Emily S.; Leenaars, Marlies

    2014-01-01

    The question of how animal studies should be designed, conducted, and analyzed remains underexposed in societal debates on animal experimentation. This is not only a scientific but also a moral question. After all, if animal experiments are not appropriately designed, conducted, and analyzed, the results produced are unlikely to be reliable and the animals have in effect been wasted. In this article, we focus on one particular method to address this moral question, namely systematic reviews of previously performed animal experiments. We discuss how the design, conduct, and analysis of future (animal and human) experiments may be optimized through such systematic reviews. In particular, we illustrate how these reviews can help improve the methodological quality of animal experiments, make the choice of an animal model and the translation of animal data to the clinic more evidence-based, and implement the 3Rs. Moreover, we discuss which measures are being taken and which need to be taken in the future to ensure that systematic reviews will actually contribute to optimizing experimental design and thereby to meeting a necessary condition for making the use of animals in these experiments justified. PMID:25541545