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Sample records for equipment addendum revision

  1. Addendum to the Safety Analysis Report for the Steel Waste Packaging. Revision 1

    International Nuclear Information System (INIS)

    Crow, S.R.

    1996-01-01

    The Battelle Pacific Northwest National Laboratory Safety Analysis Report (SAR) for the Steel Waste Package requires additional analyses to support the shipment of remote-handled radioactive waste and special-case waste from the 324 building hot cells to PUREX for interim storage. This addendum provides the analyses required to show that this waste can be safely shipped onsite in the configuration shown

  2. Addendum to the post-closure permit application for the Bear Creek Hydrogeologic Regime at the Y-12 Plant: Walk-in pits. Revision 2

    International Nuclear Information System (INIS)

    1995-04-01

    The revised Closure Plan was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits (WIPs) of the Bear Creek Burial Grounds (BCBG). However, a strategy was developed to include the B Area [a solid waste management unit (SWMU)] with the WIPs so that both areas would be closed under one cap. The plan was presented to the State of Tennessee on March 8, 1990, and the Department of Energy was requested to review other unique alternatives to close the site. Therefore, in November 1992, the Closure Plan for B Area and the WIPs was prepared separately from that of the other sites associated with the BCBG and was presented in a RCRA Closure Plan. The Closure Plan revision issued April 1993 was intended to reflect the placement of the Kerr Hollow Quarry debris at the WIPs, revise the closure data, and acknowledge that the disposition of a monitoring well within the closure site could not be verified. A Post-Closure Permit Application (PCPA) was to include the WIPs; however, at the time of submittal, closure of the WIPs had not been certified. This addendum contains information on the WIPs to accompany the BCBG PCPA. The purpose of this document is to supplement the information provided in the BCBG PCPA. This document is not intended to be a stand-alone document. Only additional information regarding the WIPs is included in the sections of this document, which correspond to sections of the PCPA submitted in June 1994

  3. WIPP conceptual design report. Addendum J. Support equipment in the high level waste facility of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Rieb, M.J.; Foley, R.S.

    1977-04-01

    The Aerojet Manufacturing Company (AMCO) received a contract in November 1976 to provide consulting services in assisting Holmes and Narver, Incorporated with the conceptual designs, cost estimates, and schedules of equipment used to handle waste casks, to decontaminate waste canisters and to overpack damaged or highly contaminated waste canisters for the Waste Isolation Pilot Plant (WIPP). Also, the layout of the hot cell in which canister handling, overpack and decontamination takes place was to be reviewed along with the time and motion study of the cell operations. This report has been prepared to present the results of the efforts and contains all technical and planning data developed during the program. The contents of this report are presented in three sections: (1) comments on the existing design criteria, equipment conceptual designs, hot cell design and time and motion studies of projected hot cell activities; (2) design descriptions of the equipment concepts and justification for varying from the existing concept (if a variation occurred). Drawings of each concept are provided in Appendix A. These design descriptions and drawings were used as the basis for the cost estimates; and (3) schedule projections and cost estimates for the equipment described in Section 2. Detail cost estimate backup data is provided in Appendix B

  4. Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2

    Energy Technology Data Exchange (ETDEWEB)

    Abrahamson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Inhalation Toxicology Research Inst.; Gilbert, E.S. [Pacific Northwest Lab., Richland, WA (United States)

    1993-05-01

    The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for Nuclear Power Plant Consequence Analysis{close_quotes}, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled {open_quotes}Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low LET Radiation, Part 2: Scientific Bases for Health Effects Models,{close_quotes} was published in 1991 as NUREG/CR-4214, Rev. 1, Part 2, Addendum 1. This second addendum addresses the possibility that some fraction of the accident source term from an operating nuclear power plant comprises alpha-emitting radionuclides. Consideration of chronic high-LET exposure from alpha radiation as well as acute and chronic exposure to low-LET beta and gamma radiations is a reasonable extension of the health effects model.

  5. Addendum to the Closure Report for Corrective Action Unit 411: Double Tracks Plutonium Dispersion (Nellis), Nevada Test and Training Range, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Burmeister, Mark [Navarro, Las Vegas, NV (United States)

    2016-11-01

    The Corrective Action Unit (CAU) 411 Closure Report (CR) was published in June 2016 (NNSA/NFO, 2016). The purpose of this addendum is to clarify language in the CR relating to the field instrument for the detection of low-energy radiation (FIDLER), provide the waste disposal documentation for waste generated during the corrective action investigation (CAI), and reference a letter from the U.S. Air Force (USAF) regarding the closure of CAU 411.

  6. CSER 90-006, addendum 1: Criticality safety control for source term reduction project in the scrubber glovebox of Building 232-Z. Revision 1

    International Nuclear Information System (INIS)

    Hess, A.L.

    1995-01-01

    This Criticality Safety Evaluation Report addendum extends the coverage of the original CSER (90-006) about dismantling the ductwork in 232-Z to include cleanout of the Scrubber Glovebox, with an estimated residual Pu holdup of less than 200 grams. For conservatism and containment considerations, the provisions about waste packaging and water exclusion from the original work are retained, even though it is not credible for the Scrubber Pu content to be made critical with water added (NDA gives about 1/3 a minimum critical mass)

  7. Addendum to the Closure Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Lynn Kidman

    2009-02-01

    This document constitutes an addendum to the September 1998, Closure Report for Corrective Action Unit 404: Roller Coaster Lagoons and Trench, Tonopah Test Range, Nevada as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the modification of the UR for CAS TA-03-001-TARC Roller Coaster Lagoons. This UR was established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and was based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This reevaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to modify the UR for CAS TA-03

  8. Evaluation of the revised training program for senior control room staff: science fundamentals and equipment principles

    International Nuclear Information System (INIS)

    Jervis, R.E.; Evans, G.J.

    1996-10-01

    Canadian nuclear utilities have formed an Inter-Utility Working Group to revise their program for training nuclear generating station senior control room staff, namely Control Room Operators and Shift Supervisors, in Science Fundamentals and Equipment Principles. This report documents the findings of an external review of this revision process, addressing, amongst other topics, the process of revision undertaken by the Working Group, their outline of topics to be included, and, the pertinence and comprehensiveness of the detailed training objectives identified for two of the courses. The approach to revising the program being followed by the Working Group appears to be reasonable insomuch that some training needs have been identified and used to construct detailed sets of training objectives. However, as assessed by the consultants without full documentation being available, some important steps appear to have been missed. Specifically, much of the basis of the revision process has not been documented, neither has the approach selected for the revision process, nor has any justification for not performing a CANDU specific job and task analysis been offered. Furthermore, the Working Group has not yet proposed any criteria for evaluation of the program or provided any test items. As a result, the consultants have had to develop criteria for evaluation of the overall program and of individual courses. These criteria were applied in a more detailed review of the training objectives for two particular courses: Plant Chemistry, and Nuclear Physics and Reactor Theory. Many of the training objectives for these courses were found to be too qualitative or ones that require trainees to memorize blocks of information rather than develop in them an ability to arrive at conclusions about scientific phenomena using principles and reasoning. This assessment indicates that the training objectives are designed to achieve too low a level of cognition, inconsistent with developing an

  9. Addendum to the health and safety plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    International Nuclear Information System (INIS)

    Clark, C. Jr.; Burman, S.N.; Wilson, K.A.

    1995-08-01

    There are three purposes for this addendum to the health and safety plan for Waste Area Grouping 6. The first purpose is to provide record of a corrective action response concerning an occurrence on WAG 6 in October 1994 (ORO-MMES-ENVRES-1994-0016.) This occurrence involved a precautionary evacuation of subcontractor field crews due to malfunctioning monitor alarms for organic vapors. The corrective action is to revise the WAG 6 Site health and safety plan to improve communications during emergency events. The second purpose is to incorporate any outstanding health and safety issues not addressed in the original health and safety plan for WAG 6 document (ORNL/ER-183). The only variance of note is tritium air monitoring in the Tumulus building. The tritium air monitor is added in this addendum as monitoring equipment for WAG 6 with description of action level and calibration. The third purpose of this addendum is to satisfy a condition of approval for the pending Nuclear Criticality Safety Assessment (NCSA) pertaining to KEMA fuel storage at WAG 6. This approval condition requires the following: ''The location of the KEMA burial shall be recorded and maintained in a controlled document that identifies the quantity and the general physical conditions at the time of the entombment with an admonishment to obtain nuclear criticality safety guidance before altering the burial condition.'' In order to satisfy the approval, this document must be controlled. The predecessor to the pending NCSA is NSR No. 0002WM22001

  10. PAT-1 safety analysis report addendum.

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Ruth F.; Schmale, David T.; Kalan, Robert J.; Akin, Lili A.; Miller, David Russell; Knorovsky, Gerald Albert; Yoshimura, Richard Hiroyuki; Lopez, Carlos; Harding, David Cameron; Jones, Perry L.; Morrow, Charles W.

    2010-09-01

    The Plutonium Air Transportable Package, Model PAT-1, is certified under Title 10, Code of Federal Regulations Part 71 by the U.S. Nuclear Regulatory Commission (NRC) per Certificate of Compliance (CoC) USA/0361B(U)F-96 (currently Revision 9). The purpose of this SAR Addendum is to incorporate plutonium (Pu) metal as a new payload for the PAT-1 package. The Pu metal is packed in an inner container (designated the T-Ampoule) that replaces the PC-1 inner container. The documentation and results from analysis contained in this addendum demonstrate that the replacement of the PC-1 and associated packaging material with the T-Ampoule and associated packaging with the addition of the plutonium metal content are not significant with respect to the design, operating characteristics, or safe performance of the containment system and prevention of criticality when the package is subjected to the tests specified in 10 CFR 71.71, 71.73 and 71.74.

  11. Addendum to the Closure Report for Corrective Action Unit 484: Surface Debris, Waste Sites, and Burn Area, Tonopah Test Range, Nevada (Revision 0)

    International Nuclear Information System (INIS)

    Burmeister, Mark

    2011-01-01

    Corrective Action Unit (CAU) 484 Streamlined Approach for Environmental Restoration (SAFER) activities called for the identification and remediation of surface hot spot depleted uranium (DU) with some excavation to determine the vertical extent of contamination (NNSA/NSO, 2004). During the CAU 484 SAFER investigation (conducted November 2003 through August 2007), approximately 50 locations containing DU were identified on Antelope Lake. All but four locations (CA-1, SA-5-9, SA-12-15, and SA-4) were remediated. Figure 1-1 shows locations of the four use restriction (UR) sites. The four locations were determined to have failed the SAFER conceptual site model assumption of a small volume hot spot. Two of the locations (CA-1 and SA-5-9) were excavated to depths of 3.5 to 7 feet (ft) below ground surface (bgs), and a third location (SA-12-15) with a footprint of 30 by 60 ft was excavated to a depth of 0.5 ft. At the fourth site (SA-4), the discovery of unexploded ordnance (UXO) halted the excavation due to potential safety concerns. Remediation activities on Antelope Lake resulted in the removal of approximately 246 cubic yards (yd3) of DU-impacted soil from the four UR sites; however, Kiwi surveys confirmed that residual DU contamination remained at each of the four sites. (The Kiwi was a Remote Sensing Laboratory [RSL] vehicle equipped with a data-acquisition system and four sodium iodide gamma detectors. Surveys were conducted with the vehicle moving at a rate of approximately 10 miles per hour with the gamma detectors positioned 14 to 28 inches [in.] above the ground surface [NNSA/NSO, 2004]).

  12. Grøstl Addendum

    DEFF Research Database (Denmark)

    Gauravaram, Praveen; Knudsen, Lars R.; Matusiewicz, Krystian

    2009-01-01

    This document is an addendum to the submission document of Grøstl, which was selected for the second round of NIST’s SHA-3 competition [18]. We stress that we do not change the specification of Grøstl. In other words, Grøstl is defined exactly as specified in the original submission document [8]....

  13. Engineering task plan for the annual revision of the rotary mode core sampling system safety equipment list

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This Engineering Task Plan addresses an effort to provide an update to the RMCS Systems 3 and 4 SEL and DCM in order to incorporate the changes to the authorization basis implemented by HNF-SD-WM-BIO-001, Rev. 0 (Draft), Addendum 5 , Safety Analysis for Rotary Mode Core Sampling. Responsibilities, task description, cost estimate, and schedule are presented

  14. Revised

    DEFF Research Database (Denmark)

    Johannsen, Vivian Kvist; Nord-Larsen, Thomas; Riis-Nielsen, Torben

    This report is a revised analysis of the Danish data on CO2 emissions from forest, afforestation and deforestation for the period 1990 - 2008 and a prognosis for the period until 2020. Revision have included measurements from 2009 in the estimations. The report is funded by the Ministry of Climate...

  15. 77 FR 35310 - Revisions to the Export Administration Regulations (EAR): Control of Military Training Equipment...

    Science.gov (United States)

    2012-06-13

    ... for foreign made ``military commodities'' that incorporate more than 10% U.S.-origin ``600 series... Military Training Equipment and Related Items the President Determines No Longer Warrant Control Under the... longer warrant control under Category IX (Military Training Equipment and Training) of the United States...

  16. 75 FR 35786 - White River Minimum Flows-Addendum to Final Determination of Federal and Non-Federal Hydropower...

    Science.gov (United States)

    2010-06-23

    ... a revised discount rate selection for calculation of the present value of the losses for both the... determination rather than the discount rate selection proposed in the June 2009 draft addendum. Therefore, no change is required to the final determination related to the discount rate. The discount rate change...

  17. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    Energy Technology Data Exchange (ETDEWEB)

    J. Cunningham and J. Shank

    2004-11-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I&C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner.

  18. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    International Nuclear Information System (INIS)

    Cunningham, J.; Shank, J.

    2004-01-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner

  19. Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1

    International Nuclear Information System (INIS)

    Conner, J.C.

    1994-01-01

    The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required

  20. Dictionary of minor planet names addendum to 6th edition 2012-2014

    CERN Document Server

    Schmadel, Lutz D

    2015-01-01

    The quantity of numbered minor planets is now approaching half a million. Together with this Addendum, the sixth edition of the Dictionary of Minor Planet Names, which is the IAU's official reference for the field, now covers more than 19,000 named minor planets. In addition to being of practical value for identification purposes, the Dictionary of Minor Planet Names provides authoritative information about the basis for the rich and colorful variety of ingenious names, from heavenly goddesses to artists, from scientists to Nobel laureates, from historical or political figures to ordinary women and men, from mountains to buildings, as well as a variety of compound terms and curiosities. This Addendum to the 6th edition of the Dictionary of Minor Planet Names adds approximately 2200 entries. It also contains many corrections, revisions and updates to the entries published in earlier editions. This work is an abundant source of information for anyone interested in minor planets and who enjoys reading about the ...

  1. Addendum to the Composite Analysis for the E-Area Vaults and Saltstone Disposal Facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    2002-01-01

    Revision 1 of the Composite Analysis (CA) Addendum has been prepared to respond to the U.S. Department of Energy (DOE) Low-Level Waste Disposal Facilities Federal Review Group review of the CA. This addendum to the composite analysis responds to the conditions of approval. The composite analysis was performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of the Savannah River Site and contains all of the waste disposal facilities, the chemical separation facilities and associated high-level waste storage facilities, as well as numerous other sources of radioactive material

  2. Test Plan Addendum No. 1: Waste Isolation Pilot Plant bin-scale CH TRU waste tests

    International Nuclear Information System (INIS)

    Molecke, M.A.; Lappin, A.R.

    1990-12-01

    This document is the first major revision to the Test Plan: WIPP Bin-Scale CH TRU Waste Tests. Factors that make this revision necessary are described and justified in Section 1, and elaborated upon in Section 4. This addendum contains recommended estimates of, and details for: (1) The total separation of waste leaching/solubility tests from bin-scale gas tests, including preliminary details and quantities of leaching tests required for testing of Levels 1, 2, and 3 WIPP CH TRU wastes; (2) An initial description and quantification of bin-scale gas test Phase 0, added to provide a crucial tie to pretest waste characterization representatives and overall test statistical validation; (3) A revision to the number of test bins required for Phases 1 and 2 of the bin gas test program, and specification of the numbers of additional bin tests required for incorporating gas testing of Level 2 wastes into test Phase 3. Contingencies are stated for the total number of test bins required, both positive and negative, including the supporting assumptions, logic, and decision points. (4) Several other general test detail updates occurring since the Test Plan was approved and published in January, 1990. Possible impacts of recommended revisions included in this Addendum on WIPP site operations are called out and described. 56 refs., 12 tabs

  3. HAPO Plant and capital equipment budget for FY 1966 and revision of budget for FY 1965 equipment not related to construction projects

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, J.E.

    1964-05-12

    This document is divided into: byproduct horizontal control rod system (5 reactors); high-speed scanning-effluent temperature monitoring system (KE reactor); improved reactor gas system (100-KE & KW); safety circuit system modifications (5 reactors); alternate process hot die sizing, 313 Building 300 Area; button line equipment (234-5 Building); in-tank waste solidification (3rd unit); and misc. minor equipment projects.

  4. 48 CFR 1352.239-70 - Software license addendum.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Software license addendum... Software license addendum. As prescribed in 48 CFR 1339.107, insert the following clause: Software License....S.C. Section 516). (h) Renewal of Support after Expiration of this Award: Service will not...

  5. Safe Handling of Radioisotopes. Health Physics Addendum

    International Nuclear Information System (INIS)

    Appleton, G.J.; Krishnamoorthy, P.N.

    1960-01-01

    The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains technical information necessary for the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the technical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

  6. Safe Handling of Radioisotopes. Health Physics Addendum

    Energy Technology Data Exchange (ETDEWEB)

    Appleton, G J; Krishnamoorthy, P N

    1960-07-15

    The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains technical information necessary for the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the technical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

  7. Safe Handling of Radioisotopes. Medical Addendum

    International Nuclear Information System (INIS)

    Hercik, F.; Jammet, H.

    1960-01-01

    The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains information necessary to medical officers concerned with the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the medical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

  8. Industrial Technology Modernization Program. Project 44. Modernize Facility Equipment and Processes. Volume 2. Revision 2. Phase 2

    Science.gov (United States)

    1988-05-01

    not be implemented. A change in foreign exchange rates (which increase the equipment cost) and a reduction in marketing forecast resulted in an...project will not be implemented due to unfavorable changes in foreign exchange rates (which increase the equipment costs) and a reduction in market

  9. Development of floor design response spectra for seismic design of floor-supported equipment or components, Revision 1, February 1978

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    This guide presents an acceptable method for developing two horizontal and one vertical floor design response spectra at various floor or other equipment-support locations from the time-history motions resulting from the dynamic analysis of the supporting structure. These floor design response spectra are used in the dynamic analysis of systems or equipment supported at various locations of the supporting structure. Consulation has been provided by the Advisory Committee on Reactor Safeguards

  10. Addendum to the Phase 2 Sampling and Analysis Plan for the Clinch River Remedial Investigation

    International Nuclear Information System (INIS)

    1994-03-01

    This document is an addendum to the Phase 2 Sampling and Analysis Plan for the Clinch River Remedial Investigation (DOE 1993). The Department of Energy--Oak Ridge Operations (DOE-ORO) is proposing this addendum to the US Envianmental Protection Agency, Region IV (EPA-IV), and the Tennessee Department of Environment and Conservation (TDEC) as a reduced sampling program on the Clinch River arm of Watts Bar Reservoir and on Poplar Creek. DOE-ORO is proposing to maximize the use of existing data and minimize the collection of new data for water, sediment, and biota during Phase 2 of the Clinch River Remedial Investigation. The existing data along with the additional data collected in Phase 2 would be used to perform a baseline risk assessment and make remedial decisions. DOE-ORO considers that the existing data, the additional data collected in Phase 2, and on-site remedial investigation data would be sufficient to understand the nature and extent of the contamination problem in the Clinch River, perform a baseline risk assessment,and make remedial decisions. This addendum is organized in three sections. The first section provides background information and describes a rationale for modifying the Phase 2 Sampling and Analysis Plan. Section 2 presents a summary of the existing data for the Clinch River arm of Watts Bar Reservoir and an evaluation of the sufficiency of this data for a baseline human health and ecological risk assessment. Section 3 describes the revised Phase 2 Sampling and Analysis Plan for surface water, sediment, and biota in the Clinch River OU and in the Poplar Creek OU

  11. Alcator C-MOD proposal addendum

    International Nuclear Information System (INIS)

    Bonoli, P.; Greenwald, M.; Gwinn, D.

    1986-04-01

    Since the design concept and overall purpose of the Alcator C-MOD device are similar to that proposed in October 1985, we have chosen in this document only to highlight areas where changes or additions have been made. Chapters in the Addendum correspond to those in the Proposal, except Chapter 9 which describes a number of toroidal improvement concepts which are being considered for inclusion in the Alcator C-MOD experimental program. A description of the redesign and a discussion of the objectives of the experimental program are given

  12. Advancing Geographic Information Science—Proposal to NSF, with Addendum

    OpenAIRE

    National Center for Geographic Information and Analysis

    1995-01-01

    This document from 1995 and the addendum from 1996 represent NCGIA's proposal for Varenius—a program of research initiatives to advance geographic information science in the context of digitial worlds and the information society.

  13. Human Reliability Analysis for In-Tank Precipitation Alignment and Startup of Emergency Purge Ventilation Equipment. Revision 4

    International Nuclear Information System (INIS)

    Shapiro, B.J.; Britt, T.E.

    1995-06-01

    This report documents the methodology used for calculating the human error probability for establishing air based ventilation using emergency purge ventilation equipment on In-Tank Precipitation (ITP) processing tanks 48 and 49 after a failure of the nitrogen purge system following a seismic event. The analyses were performed according to THERP (Technique for Human Error Rate Prediction) as describes in NUREG/CR-1278-F

  14. Human Reliability Analysis for In-Tank Precipitation Alignment and Startup of Emergency Purge Ventilation Equipment. Revision 3

    International Nuclear Information System (INIS)

    Shapiro, B.J.; Britt, T.E.

    1994-10-01

    This report documents the methodology used for calculating the human error probability for establishing air based ventilation using emergency purge ventilation equipment on In-Tank Precipitation (ITP) processing tanks 48 and 49 after failure of the nitrogen purge system following a seismic event. The analyses were performed according to THERP (Technique for Human Error Rate Prediction) as described in NUREG/CR-1278-F, ''Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications.'' The calculated human error probabilities are provided as input to the Fault Tree Analysis for the ITP Nitrogen Purge System

  15. GPHS-RTGs in support of the Cassini RTG Program. Addendum to the final technical report, May 1--December 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    This Addendum to the Cassini GPHS-RTG Program Final Technical Progress Report describes activities performed during the period 1 May 1998 through 31 December 1998, including effort reflecting contract modification M058. These activities include Earth Gravity Assist (EGA) reentry and related analyses which are detailed in Part A, and effort related to the installation of CAGO equipment within Lockheed Martin`s Building 100 facility in Valley Forge, PA, which is detailed in Part B.

  16. GPHS-RTGs in support of the Cassini RTG Program. Addendum to the final technical report, May 1-December 31, 1998

    International Nuclear Information System (INIS)

    1998-12-01

    This Addendum to the Cassini GPHS-RTG Program Final Technical Progress Report describes activities performed during the period 1 May 1998 through 31 December 1998, including effort reflecting contract modification M058. These activities include Earth Gravity Assist (EGA) reentry and related analyses which are detailed in Part A, and effort related to the installation of CAGO equipment within Lockheed Martin's Building 100 facility in Valley Forge, PA, which is detailed in Part B

  17. Hanford Tank Farms Vadose Zone, Addendum to the TX Tank Farm Report

    International Nuclear Information System (INIS)

    Spatz, R.

    2000-01-01

    This addendum to the TX Tank Farm Report (GJO-97-13-TAR, GJO-HAN-11) published in September 1997 incorporates the results of high-rate and repeat logging activities along with shape factor analysis of the logging data. A high-rate logging system was developed and deployed in the TX Tank Farm to measure cesium-137 concentration levels in high gamma flux zones where the spectral gamma logging system was unable to collect usable data because of high dead times and detector saturation. This report presents additional data and revised visualizations of subsurface contaminant distribution in the TX Tank Farm at the DOE Hanford Site in the state of Washington

  18. Hanford Tank Farms Vadose Zone, Addendum to the T Tank Farm Report

    Energy Technology Data Exchange (ETDEWEB)

    Spatz, Robert

    2000-07-01

    This addendum to the T Tank Farm Report (GJO-99-101-TARA, GJO-HAN-27) published in September 1999 incorporates the results of high-rate and repeat logging activities along with shape factor analysis of the logging incorporates the results of high-rate and repeat logging activities along with shape factor analysis of the logging data. A high-rate logging system was developed and deployed in the T Tank Farm to measure cesium-137 concentration levels in high gamma flux zones where the spectral gamma logging system was unable to collect usable data because of high dead times and detector saturation. This report presents additional data and revised visualizations of subsurface contaminant distribution in the T Tank Farm at the DOE Hanford Site in the state of Washington.

  19. ARIADNE: Beam Time and Resources Request - Addendum

    CERN Document Server

    Hollywood, D; Mavrokoridis, K; McCormick, KJ; Philippou, B; Roberts, A; Stavrakis, G; Touramanis, C; Vann, J

    2017-01-01

    This addendum provides additional information and clarification requested by the SPS Committee in response to our previously submitted Beam Time Request (CERN-SPSC-2017-031 [SPSC-P-356]). The ARIADNE research programme is based around developing an optical readout system for use in LAr TPC detectors, which could potentially have a number of benefits over the currently used segmented anode planes - particularly in matters of scalability for future kilo-tonne scale detectors, ease of installation, use and maintenance, and reconstruction resolution. As detailed in our previously submitted Letter of Intent (CERN-SPSC-2016-008 [SPSC-I-244]), ARIADNE itself is a 1-tonne, two-phase LAr TPC detector, designed and built at the University of Liverpool, which uses an array of EMCCD cameras as its optical readout system, alongside PMTs for scintillation light observation and a segmented THGEM for charge readout.

  20. Addendum to the post-closure permit application for the Bear Creek hydrogeologic regime at the Y-12 plant: Walk-in pits

    International Nuclear Information System (INIS)

    1995-04-01

    In June 1987, the Resource Conservation and Recovery Act (RCRA) Closure/Post-Closure Plan for the Bear Creek Burial Grounds (BCBG) located at the Y-12 Plant on the Oak Ridge Reservation in Oak Ridge, Tennessee was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval.The Closure Plan has been modified and revised several times. This document is an addendum to the Post-Closure Permit Application submitted to TDEC in June, 1994. This addendum contains information on the Walk-In Pits of the BCBG which is meant to supplement the information provided in the Post-Closure Permit Application submitted for the BCBG. This document is not intended to be a stand-alone document.

  1. Addendum report of the JHPS expert committee on radiation protection of the lens of the eye (3). Recent related overseas activities

    International Nuclear Information System (INIS)

    Akahane, Keiichi; Tatsuzaki, Hideo; Iimoto, Takeshi; Ichiji, Takeshi; Hamada, Nobuyuki; Iwai, Satoshi; Ohguchi, Hiroyuki; Ohno, Kazuko; Kawaura, Chiyo; Tsujimura, Norio; Hotta, Yutaka; Yamasaki, Tadashi; Yokoyama, Sumi

    2015-01-01

    Following the Statement on Tissue Reaction issued by the International Commission on Radiological Protection (ICRP), revisions and discussions are underway in various international organizations about the standards, guidelines and methods for the eye dosimetry. We have previously discussed these issues in six interim reports, followed by two addendum reports on lens dosimetry. This addendum report reviews ongoing overseas discussion and work in relation to research on radiogenic cataracts and implementation of the new eye lens dose limit, such as those in the European Commission, Low Dose Research towards Multidisciplinary Integration (DoReMi), Open Project for European Radiation Research Area (OPERRA), and the Unite Sates National Council on Radiation Protection and Measurements (NCRP). This report serves as the last part of a series of reports by the Japan Health Physics Society Expert Committee on Radiation Protection of the Lens of the Eye. (author)

  2. TU-D-201-03: Results of a Survey On the Implementation of the TG-51 Protocol and Associated Addendum On Reference Dosimetry of External Beams

    Energy Technology Data Exchange (ETDEWEB)

    Kim, G [University of California, San Diego, La Jolla, CA (United States); Muir, B [National Research Council, Ottawa, AB (Canada); Culberson, W [University of Wisconsin Madison, Madison, WI (United States); Davis, S [McGill University Health Center, Montreal, QC (Canada); Huang, Y [Henry Ford Health System, West Bloomfield, MI (United States); Lee, S [University of Maryland School of Medicine, Columbia, MD (United States); Lowenstein, J [UT MD Anderson Cancer Center, Houston, TX (United States); Sarfehnia, A [Sunnybrook Health Science Center, Toronto, ON (Canada); Tolani, N [Michael E. DeBakey VA Medical Center, Sugarland (United States); Siebers, J [University of Virginia Health System, Charlottesville, VA (United States)

    2016-06-15

    Purpose: The working group on the review and extension of the TG-51 protocol (WGTG51) collected data from American Association of Physicists in Medicine (AAPM) members with respect to their current TG-51 and associated addendum usage in the interest of considering future protocol addenda and guidance on reference dosimetry best practices. This study reports an overview of this survey on dosimetry of external beams. Methods: Fourteen survey questions were developed by WGTG51 and released in November 2015. The questions collected information on reference dosimetry, beam quality specification, and ancillary calibration equipment. Results: Of the 190 submissions completed worldwide (U.S. 70%), 83% were AAPM members. Of the respondents, 33.5% implemented the TG-51 addendum, with the maximum calibration difference for any photon beam, with respect to the original TG-51 protocol, being <1% for 97.4% of responses. One major finding is that 81.8% of respondents used the same cylindrical ionization chamber for photon and electron dosimetry, implying that many clinics are foregoing the use of parallel-plate chambers. Other evidence suggests equivalent dosimetric results can be obtained with both cylindrical and parallel-plate chambers in electron beams. This, combined with users comfort with cylindrical chambers for electrons will likely impact recommendations put forward in an upcoming electron beam addendum to the TG-51 protocol. Data collected on ancillary equipment showed 58.2% (45.0%) of the thermometers (barometers) in use for beam calibration had NIST traceable calibration certificates, but 48.4% (42.7%) were never recalibrated. Conclusion: This survey provides a snapshot of TG-51 external beam reference dosimetry practice in radiotherapy centers. Findings demonstrate the rapid take-up of the TG-51 photon beam addendum and raise issues for the WGTG51 to focus on going forward, including guidelines on ancillary equipment and the choice of chamber for electron beam

  3. Addendum to the 2015 Eastern Interconnect Baselining and Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Amidan, Brett G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Follum, James D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-06-30

    This report serves as an addendum to the report 2015 Eastern Interconnect Baselining and Analysis Report (Amidan, Follum, and Freeman, 2015). This addendum report investigates the following: the impact of shorter record lengths and of adding a daily regularization term to the date/time models for angle pair measurements, additional development of a method to monitor the trend in phase angle pairs, the effect of changing the length of time to determine a baseline, when calculating atypical events, and a comparison between quantitatively discovered atypical events and actual events.

  4. Addendum to Environmental Monitoring Plan, Nevada Test Site and Support Facilities; Addendum 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-11-01

    This 1993 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/10630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Operations Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1993 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  5. Fuel Receiving and Storage Station. License application, amendment 5, addendum

    International Nuclear Information System (INIS)

    1975-06-01

    This Addendum to AG-L105 addresses the utilization of the Service Concentrator for evaporation of low level wastes generated during fuel receiving and storage operations. The Service Concentrator is described from various viewpoints and necessary relevant data are included for adequate assessment of safety. (U.S.)

  6. 78 FR 39763 - Recovery Plan Addendum; Thick-Billed Parrot

    Science.gov (United States)

    2013-07-02

    ... particular species. Species' History Historically the thick-billed parrot's range extended from Mexico into... and the Secretary of the Interior. This species is currently found in Mexico but has not been detected... included southern Arizona and possibly southwestern New Mexico. The recovery plan addendum includes...

  7. Integrated thermal treatment system study. Phase 2. Addendum system A8

    International Nuclear Information System (INIS)

    Biagi, C.; Teheranian, B.; Quapp, W.J.; Schwinkendorf, W.E.

    1996-05-01

    This is an addendum to the Integrated Treatment System Study - Phase 2 Results report. This addendum describes the technology and the operation of System A-8, Rotary Kiln, Air Combustion Gas, Dry-Wet APC, and Grout Stabilization. A process flow diagram, functional allocation diagrams, and plan views and perspective views for this system are attached. Detailed cost information for this subsystem is reported in Appendix A of this addendum

  8. Addendum to the remedial investigation report on Bear Creek Valley Operable Unit 2 (Rust Spoil Area, Spoil Area 1, and SY-200 Yard) at the Oak Ridge Y-12 Plant Oak Ridge, Tennessee. Volume 1: Main text

    International Nuclear Information System (INIS)

    1995-04-01

    This addendum to the Remedial Investigation (RI) Report on Bear Creek Valley Operable Unit (OU) 2 at the Oak Ridge Y-12 Plant was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting the results of a site characterization for public review. This addendum is a supplement to a document that was previously issued in January 1995 and that provided the Environmental Restoration Program with information about the results of the 1993 investigation performed at OU 2. The January 1995 D2 version of the RI Report on Bear Creek Valley OU 2 included information on risk assessments that have evaluated impacts to human health and the environment. Information provided in the document formed the basis for the development of the Feasibility Study Report. This addendum includes revisions to four chapters of information that were a part of the document issued in January 1995. Specifically, it includes revisions to Chaps. 2, 3, 4, and 9. Volume 1 of this document is not being reissued in its entirety as a D3 version because only the four chapters just mentioned have been affected by requested changes. Note also that Volume 2 of this RI Report on Bear Creek Valley OU 2 is not being reissued in conjunction with Volume 1 of this document because there have been no changes requested or made to the previously issued version of Volume 2 of this document.

  9. Addendum to 'Reconciling grand unification with strings by anisotropic compactifications'

    International Nuclear Information System (INIS)

    Dundee, Ben; Raby, Stuart; Wingerter, Akin

    2009-01-01

    In this brief addendum, we clarify a point which we left unaddressed in a previous publication [Phys. Rev. D 78, 066006 (2008)]. In particular, we show that a specific vacuum configuration constructed in one of our models satisfies the condition D=0. In the previous publication, we only showed F=0. Both D=0 and F=0 are necessary to ensure that supersymmetry survives to the weak scale.

  10. EFSA ; Scientific Opinion on Flavouring Group Evaluation 94, Revision 1 (FGE.94Rev1): Consideration of aliphatic amines and amides evaluated in an addendum to the group of aliphatic and aromatic amines and amides evaluated by the JECFA (68th meeting)

    DEFF Research Database (Denmark)

    Larsen, John Christian; Nørby, Karin Kristiane; Beltoft, Vibe Meister

    evaluation is necessary, as laid down in Commission Regulation (EC) No 1565/2000. The present consideration concerns a group of 12 aliphatic amines and amides evaluated by the JECFA at the 68th meeting in 2007. This revision of the consideration is made due to additional toxicity data available for two...

  11. Addendum to the Closure Report for Corrective Action Unit 113: Area 25 R-MAD Facility, Nevada National Security Site, Nevada

    International Nuclear Information System (INIS)

    2011-01-01

    This addendum to the Closure Report for Corrective Action Unit 113: Area 25, Reactor Maintenance, Assembly, and Disassembly Facility, Building 3110, Nevada Test Site, Nevada, DOE/NV--891-VOL I-Rev. 1, dated July 2003, provides details of demolition, waste disposal, and use restriction (UR) modification for Corrective Action Unit 113, Area 25 R-MAD Facility. Demolition was completed on July 15, 2010, when the last of the building debris was disposed. Final field activities were concluded on August 30, 2010, after all equipment was demobilized and UR signs were posted. This work was funded by the American Recovery and Reinvestment Act.

  12. Addendum to the 1996 Gunnison Monitoring Report for the Gunnison, Colorado Wetlands Mitigation Plan

    International Nuclear Information System (INIS)

    1997-10-01

    This document is an addendum to the 1996 Gunnison Monitoring Report for the Gunnison, Colorado, Wetlands Mitigation Report, dated July 1997. The purpose of this addendum is to: (1) modify how information on plant height and plant species criteria are presented; and (2) provide more detailed information regarding the evaluation of the bare ground criteria at the Camp Ketle site. The information in this addendum is provided at the request of the Bureau of Land Management to aid in future monitoring and evaluation of the wetland mitigation sites

  13. Emergency Victim Care. A Training Manual for Emergency Medical Technicians. Module 2. Equipment, Safe Driving Practices, Legal Aspects, Controlling the Situation, Action Evaluation Conference. Revised.

    Science.gov (United States)

    Ohio State Dept. of Education, Columbus. Div. of Vocational Education.

    This student manual, the second in a set of 14 modules, is designed to train emergency medical technicians (EMTs) in Ohio. The module contains five sections that cover the following course content: ambulance equipment, safe driving practices for emergency vehicle drivers, legal aspects of the EMT's job, how to maintain control at an accident scene…

  14. Addendum: Observables for general relativity related to geometry

    International Nuclear Information System (INIS)

    Duch, Paweł; Kamiński, Wojciech; Lewandowski, Jerzy; Świeżewski, Jędrzej

    2015-01-01

    In this addendum we clarify a point which strengthens one of the results from http://dx.doi.org/10.1007/JHEP05(2014)077. Namely, we show that the algebra of the observables F(r,θ) is yet simpler then it was described in http://dx.doi.org/10.1007/JHEP05(2014)077. This is an important point, because with this simplification an important subalgebra becomes canonical, allowing for a natural reduction of the phase space.

  15. Statement of Agreements Registered with the Agency. Addendum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-10-24

    This addendum is divided into two parts. Part I contains supplementary information on certain agreements which were registered with the Agency up to 30 June 1960; part II is a statement of all agreements so registered between July 1960 and 30 June 1961. In compliance with Article VI of the Regulations for the Registration of Agreements this document is hereby transmitted to all Members of the Agency for their information. A copy is also being sent to the Secretary-General of the United Nations.

  16. Statement of Agreements Registered with the Agency. Addendum

    International Nuclear Information System (INIS)

    1961-01-01

    This addendum is divided into two parts. Part I contains supplementary information on certain agreements which were registered with the Agency up to 30 June 1960; part II is a statement of all agreements so registered between July 1960 and 30 June 1961. In compliance with Article VI of the Regulations for the Registration of Agreements this document is hereby transmitted to all Members of the Agency for their information. A copy is also being sent to the Secretary-General of the United Nations

  17. Addendum: Observables for general relativity related to geometry

    Energy Technology Data Exchange (ETDEWEB)

    Duch, Paweł [Institute of Physics, Jagiellonian University,Reymonta 4, 30-059 Kraków (Poland); Kamiński, Wojciech [Faculty of Physics, University of Warsaw,Hoża 69, 00-681 Warszawa (Poland); Lewandowski, Jerzy [Faculty of Physics, University of Warsaw,Hoża 69, 00-681 Warszawa (Poland); Institute for Quantum Gravity (IQG), FAU Erlangen - Nurnberg,Staudtstr. 7, 91058 Erlangen (Germany); Świeżewski, Jędrzej [Faculty of Physics, University of Warsaw,Hoża 69, 00-681 Warszawa (Poland)

    2015-04-15

    In this addendum we clarify a point which strengthens one of the results from http://dx.doi.org/10.1007/JHEP05(2014)077. Namely, we show that the algebra of the observables F(r,θ) is yet simpler then it was described in http://dx.doi.org/10.1007/JHEP05(2014)077. This is an important point, because with this simplification an important subalgebra becomes canonical, allowing for a natural reduction of the phase space.

  18. Addendum to Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Bergeron, Marcel P.; Freeman, Eugene J.; Wurstner, Signe K.; Kincaid, Charles T.; Coony, Mike M.; Strenge, Dennis L.; Aaberg, Rosanne L.; Eslinger, Paul W.

    2001-09-28

    This report summarizes efforts to complete an addendum analysis to the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis). This document describes the background and performance objectives of the Composite Analysis and this addendum analysis. The methods used, results, and conclusions for this Addendum analysis are summarized, and recommendations are made for work to be undertaken in anticipation of a second analysis.

  19. Addendum to 'Half coalescence of the m=1, n=1 magnetic island in tokamaks'

    International Nuclear Information System (INIS)

    Bussac, M.N.; Pellat, R.

    1985-01-01

    As an addendum to our previous work concerning the half-coalescence instability of an m=1, n=1 magnetic island in tokamaks, the potential energy is given for an arbitrary shape of the separatrix. (orig.)

  20. 77 FR 7131 - Addendum to Environmental Technologies Trade Advisory Committee Public Meeting

    Science.gov (United States)

    2012-02-10

    ... DEPARTMENT OF COMMERCE International Trade Administration Addendum to Environmental Technologies... agenda of a meeting of the Environmental Technologies Trade Advisory Committee (ETTAC) will be changed to... & Environmental Industries, International Trade Administration, Room 4053, 1401 Constitution Avenue NW...

  1. Effect of the Operation of Kerr and Hungry Horse Dams on the Reproductive Success of Kokanee in the Flathead System; Technical Addendum to the Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, Will; Tohtz, Joel

    1990-03-01

    This addendum to the Final Report presents results of research on the zooplankton and fish communities of Flathead Lade. The intent of the Study has been to identify the impacts of hydroelectric operations at Kerr and Hungry Horse Dam on the reproductive success of kokanee an to propose mitigation for these impacts. Recent changes in the trophic ecology of the lake, have reduced the survival of kokanee. In the last three year the Study has been redirected to identify, if possible, the biological mechanisms which now limit kokanee survival, and to test methods of enhancing the kokanee fishery by artificial supplementation. These studies were necessary to the formulation of mitigation plans. The possibility of successfully rehabilitating the kokanee population, is the doubt because of change in the trophic ecology of the system. This report first presents the results of studies of the population dynamics of crustacean zooplankton, upon which planktivorous fish depend. A modest effort was directed to measuring the spawning escapement of kokanee in 1988. Because of its relevance to the study, we also report assessments of 1989 kokanee spawning escapement. Hydroacoustic assessment of the abundance of all fish species in Flathead Lake was conducted in November, 1988. Summary of the continued efforts to document the growth rates and food habits of kokanee and lake whitefish are included in this report. Revised kokanee spawning and harvest estimates, and management implications of the altered ecology of Flathead Lake comprise the final sections of this addendum. 83 refs., 20 figs., 25 tabs.

  2. Stormwater Pollution Prevention Plan for the TA-60-01 Heavy Equipment Shop, Los Alamos National Laboratory, Revision 3, January 2018

    Energy Technology Data Exchange (ETDEWEB)

    Burgin, Jillian Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-01

    This Storm Water Pollution Prevention Plan (SWPPP) was developed in accordance with the provisions of the Clean Water Act (33 U.S.C. §§1251 et seq., as amended), and the Multi-Sector General Permit for Storm Water Discharges Associated with Industrial Activity (U.S. EPA, June 2015) issued by the U.S. Environmental Protection Agency (EPA) for the National Pollutant Discharge Elimination System (NPDES) and using the industry specific permit requirements for Sector P-Land Transportation and Warehousing as a guide. This SWPPP applies to discharges of stormwater from the operational areas of the TA-60-01 Heavy Equipment Shop at Los Alamos National Laboratory. Los Alamos National Laboratory (also referred to as LANL or the “Laboratory”) is owned by the Department of Energy (DOE), and is operated by Los Alamos National Security, LLC (LANS). Throughout this document, the term “facility” refers to the TA-60-01 Heavy Equipment Shop and associated areas. The current permit expires at midnight on June 4, 2020.

  3. EPR first responders revision test

    International Nuclear Information System (INIS)

    2011-01-01

    In this revision test evaluates the acquired knowledge in case of radiological emergency confront. Actions to be taken in relation to people, equipment and the environment. Doses, radioactive sources, pollution

  4. 78 FR 57873 - 60-Day Notice of Proposed Information Collection: HUD-Owned Real Estate-Sales Contract and Addendums

    Science.gov (United States)

    2013-09-20

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5687-N-36] 60-Day Notice of Proposed Information Collection: HUD-Owned Real Estate--Sales Contract and Addendums AGENCY: Office of the Assistant... Information Collection Title of Information Collection: HUD-Owned Real Estate--Sales Contract and Addendums...

  5. Characterization equipment essential drawing plan

    International Nuclear Information System (INIS)

    WILSON, G.W.

    1999-01-01

    The purpose of this document is to list the Characterization equipment drawings that are classified as Essential Drawings. Essential Drawings: Are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment (HNF 1997a). The Characterization equipment drawings identified in this report are deemed essential drawings as defined in HNF-PRO-242, Engineering Drawing Requirements (HNF 1997a). These drawings will be prepared, revised, and maintained per HNF-PRO-440, Engineering Document Change Control (HNF 1997b). All other Characterization equipment drawings not identified in this document will be considered Support drawings until the Characterization Equipment Drawing Evaluation Report is completed

  6. Addendum: First injection technique recommendations for patients with diabetes, Forum for Injection Techniques India

    Directory of Open Access Journals (Sweden)

    Sanjay Kalra

    2013-01-01

    Full Text Available The forum for injection techniques, India recommendation, the first ever in the country on insulin injcetion techniques, have covered the science and the art of insulin injection technique in an exhaustive manner. However, a few gaps were identified in the document, which are addressed in the current addendum. This article focuses on insulin injection technique in special clinical situations, including geriatric people, women in pregnancy and those with dermatological or surgical disease who live with diabetes. The addendum also covers salient features of administration of insulin using the insulin pump.

  7. [DOE method for evaluating environmental and waste management samples: Revision 1, Addendum 1

    International Nuclear Information System (INIS)

    Goheen, S.C.

    1995-04-01

    The US Dapartment of Energy's (DOE's) environmental and waste management (EM) sampling and analysis activities require that large numbers of samples be analyzed for materials characterization, environmental surveillance, and site-remediation programs. The present document, DOE Methods for Evaluating Environmental and Waste Management Samples (DOE Methods), is a supplemental resource for analyzing many of these samples

  8. [DOE method for evaluating environmental and waste management samples: Revision 1, Addendum 1

    Energy Technology Data Exchange (ETDEWEB)

    Goheen, S.C.

    1995-04-01

    The US Dapartment of Energy`s (DOE`s) environmental and waste management (EM) sampling and analysis activities require that large numbers of samples be analyzed for materials characterization, environmental surveillance, and site-remediation programs. The present document, DOE Methods for Evaluating Environmental and Waste Management Samples (DOE Methods), is a supplemental resource for analyzing many of these samples.

  9. Savannah River Site Environmental Monitoring Plan. Volume 1, Section 1000 Addendum: Revision 3

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1994-01-01

    This document -- the Savannah River Site Environmental Monitoring Plan (SRS EM Plan) -- has been prepared according to guidance contained in the DOE 5400 Series orders, in 10 CFR 834, and in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and environmental Surveillance [DOE, 1991]. The SRS EM Plan's purpose is to define the criteria, regulations, and guideline requirements with which SRS will comply. These criteria and requirements are applicable to environmental monitoring activities performed in support of the SRS Environmental Monitoring Program (SRS EM Program), WSRC-3Q1-2, Volume 1, Section 1100. They are not applicable to monitoring activities utilized exclusively for process monitoring/control. The environmental monitoring program requirements documented in the SRS EM Plan incorporate all applicable should requirements of DOE/EH-0173T and expand upon them to include nonradiological environmental monitoring program requirements

  10. Waste Isolation Pilot Plant No-migration variance petition. Addendum: Volume 7, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program.

  11. Addendum to: Derivation of in situ opalinus clay porewater compositions from experimental and geochemical modelling studies

    International Nuclear Information System (INIS)

    Bradbury, M.H.; Baeyens; Pearson, F.J.; Berner, U.

    1998-01-01

    As part of the synthesis of water chemistry studies within the hydrochemical program at Mont Terri (Switzerland), a reexamination of the modelling method showed that it should lead to a range of water compositions rather than to a single composition. The single composition resulted from two compensating oversights, a theoretical one and a modelling one. These are discussed in this Addendum. (author)

  12. 2011 Addendum to the SNL/NM SWEIS Supplemental Information Source Documents

    Energy Technology Data Exchange (ETDEWEB)

    Dimmick, Ross [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    This document contains updates to the Supplemental Information Sandia National Laboratories/New Mexico Site-Wide Environmental Impact Statement Source Documents that were developed in 2010. In general, this addendum provides calendar year 2010 data, along with changes or additions to text in the original documents.

  13. Reference Mission Version 3.0 Addendum to the Human Exploration of Mars: The Reference Mission of the NASA Mars Exploration Study Team. Addendum; 3.0

    Science.gov (United States)

    Drake, Bret G. (Editor)

    1998-01-01

    This Addendum to the Mars Reference Mission was developed as a companion document to the NASA Special Publication 6107, "Human Exploration of Mars: The Reference Mission of the NASA Mars Exploration Study Team." It summarizes changes and updates to the Mars Reference Missions that were developed by the Exploration Office since the final draft of SP 6107 was printed in early 1999. The Reference Mission is a tool used by the exploration community to compare and evaluate approaches to mission and system concepts that could be used for human missions to Mars. It is intended to identify and clarify system drivers, significant sources of cost, performance, risk, and schedule variation. Several alternative scenarios, employing different technical approaches to solving mission and technology challenges, are discussed in this Addendum. Comparing alternative approaches provides the basis for continual improvement to technology investment plan and a general understanding of future human missions to Mars. The Addendum represents a snapshot of work in progress in support of planning for future human exploration missions through May 1998.

  14. Revising Translations

    DEFF Research Database (Denmark)

    Rasmussen, Kirsten Wølch; Schjoldager, Anne

    2011-01-01

    The paper explains the theoretical background and findings of an empirical study of revision policies, using Denmark as a case in point. After an overview of important definitions, types and parameters, the paper explains the methods and data gathered from a questionnaire survey and an interview...... survey. Results clearly show that most translation companies regard both unilingual and comparative revisions as essential components of professional quality assurance. Data indicate that revision is rarely fully comparative, as the preferred procedure seems to be a unilingual revision followed by a more...... or less comparative rereading. Though questionnaire data seem to indicate that translation companies use linguistic correctness and presentation as the only revision parameters, interview data reveal that textual and communicative aspects are also considered. Generally speaking, revision is not carried...

  15. Equipment considerations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Trace or ultratrace analyses require that the HPLC equipment used, including the detector, be optimal for such determinations. HPLC detectors are discussed at length in Chapter 4; discussion here is limited to the rest of the equipment. In general, commercial equipment is adequate for trace analysis; however, as the authors approach ultratrace analysis, it becomes very important to examine the equipment thoroughly and optimize it, where possible. For this reason they will review the equipment commonly used in HPLC and discuss the optimization steps. Detectability in HPLC is influenced by two factors (1): (a) baseline noise or other interferences that lead to errors in assigning the baseline absorbance; (b) peak width. 87 refs

  16. The management of radioactive wastes produced by radioisotope users. Technical addendum

    International Nuclear Information System (INIS)

    1966-01-01

    This Addendum contains detailed technical information on processes and procedures that are outlined in more general terms in the Code of Practice. The information is particularly relevant to the problem of handling the relatively small quantities of waste arising from the use of radionuclides in laboratories, hospitals and industry when no special facilities for radioactive waste treatment are available on site. The Addendum is directed toward providing the radioisotope user with the type and amount of information required for him to be able to assess the alternatives available to him in terms of his particular needs, develop a preliminary design of an optimum waste-handling system and get help and guidance in his search for more detailed information.

  17. Sierra/SolidMechanics 4.48 User's Guide: Addendum for Shock Capabilities.

    Energy Technology Data Exchange (ETDEWEB)

    Plews, Julia A.; Crane, Nathan K; de Frias, Gabriel Jose; Le, San; Littlewood, David John; Merewether, Mark Thomas; Mosby, Matthew David; Pierson, Kendall H.; Porter, Vicki L.; Shelton, Timothy; Thomas, Jesse David; Tupek, Michael R.; Veilleux, Michael; Xavier, Patrick G.

    2018-03-01

    This is an addendum to the Sierra/SolidMechanics 4.48 User's Guide that documents additional capabilities available only in alternate versions of the Sierra/SolidMechanics (Sierra/SM) code. These alternate versions are enhanced to provide capabilities that are regulated under the U.S. Department of State's International Traffic in Arms Regulations (ITAR) export-control rules. The ITAR regulated codes are only distributed to entities that comply with the ITAR export-control requirements. The ITAR enhancements to Sierra/SM in- clude material models with an energy-dependent pressure response (appropriate for very large deformations and strain rates) and capabilities for blast modeling. Since this is an addendum to the standard Sierra/SM user's guide, please refer to that document first for general descriptions of code capability and use.

  18. Addendum to ''Test Plan: Small-Scale Seal Performance Tests (SSSPT)''

    International Nuclear Information System (INIS)

    Finley, R.E.

    1992-01-01

    This document describes activities that are intended to update the data base of fluid flow measurements made on expansive salt concrete (ESC) seals as part of the Small-Scale Seal Performance Tests (SSSPT). The original plans for the SSSPT experiments are described by Stormont (1985a and 1985b). These seals have previously been tested with brine and gas during the early stages (less than 450 days) after emplacement. The purpose of this Test Plan Addendum is to detail the activities necessary to, update the gas and brine measurements previously performed on the SSSPT Series A and Series B seals and to identify the key personnel responsible for implementing these activities. This addendum describes a limited undertaking and does NOT change the scope of the original test plan

  19. Addendum 6 to CSAR 79-038 out-of-hood plutonium storage (burial box)

    International Nuclear Information System (INIS)

    Chiao, T.

    1995-01-01

    The Addendum considered an increase in the limit of fissile material in a stacked container array to 500 grams. In other words, the sum of fissile material in an array of containers is limited to 500 grams, regardless of whether the containers are stacked or not. The results of this evaluation indicates that with the modification of the fissile limits described, the system of a container array will stay sub-critical

  20. Dictionary of Minor Planet Names Addendum to Fifth Edition: 2006 - 2008

    CERN Document Server

    Schmadel, Lutz

    2009-01-01

    The second Addendum to the Dictionary of Minor Planet Names, fifth edition, which is the IAU's official reference for the field, contains all newly published names from the period 2006-2008 as well as corrections and amendments to earlier editions. In total the Dictionary of Minor Planet Names now covers some 15000 named minor planets. It provides authoritative information about the basis for the rich and colorful variety of ingenious names, from heavenly goddesses to more prosaic constructions.

  1. In Vitro Osteoblast Model for Bone Wound Infections and Antimicrobial Therapy (Addendum)

    Science.gov (United States)

    2012-01-01

    n=2). Previous investigations on bacterial arthritis induced by S . aureus and S . agalactiae have suggested that TNFα, interleukin1β, and IL6, are...REPOR PREPARED FOR DISTRIBUTION S Approved fo The views, opinio should not be con unless so designa January 2012 T: Addendum to Final : U.S...contained in this report are those of the author( s ) and strued as an official Department of the Army position, policy or decision ted by other

  2. Trainees May Add Value to Patient Care by Decreasing Addendum Utilization in Radiology Reports.

    Science.gov (United States)

    Balthazar, Patricia; Konstantopoulos, Christina; Wick, Carson A; DeSimone, Ariadne K; Tridandapani, Srini; Simoneaux, Stephen; Applegate, Kimberly E

    2017-11-01

    The purpose of this study was to evaluate the impact of trainee involvement and other factors on addendum rates in radiology reports. This retrospective study was performed in a tertiary care pediatric hospital. From the institutional radiology data repository, we extracted all radiology reports from January 1 to June 30, 2016, as well as trainee (resident or fellow) involvement, imaging modality, patient setting (emergency, inpatient, or outpatient), order status (routine vs immediate), time of interpretation (regular work hours vs off-hours), radiologist's years of experience, and sex. We grouped imaging modalities as advanced (CT, MRI, and PET) or nonadvanced (any modality that was not CT, MRI, or PET) and radiologist experience level as ≤ 20 years or > 20 years. Our outcome measure was the rate of addenda in radiology reports. Statistical analysis was performed using multivariate logistic regression. From 129,033 reports finalized during the study period, 418 (0.3%) had addenda. Reports generated without trainees were 12 times more likely than reports with trainee involvement to have addenda (odds ratio [OR] = 12.2, p use (OR = 4.7, p use than those in an inpatient setting (OR = 1.5, p = 0.04; and OR = 1.3, p = 0.04, respectively). Routine orders had a slightly higher likelihood of addendum use compared with immediate orders (OR = 1.3, p = 0.01). We found no difference in addendum use by radiologist's sex, radiologist's years of experience, emergency versus outpatient setting, or time of interpretation. Trainees may add value to patient care by decreasing addendum rates in radiology reports.

  3. Addendum Guidelines for the Prevention of Peanut Allergy in the United States

    Science.gov (United States)

    Togias, Alkis; Cooper, Susan F.; Acebal, Maria L.; Assa’ad, Amal; Baker, James R.; Beck, Lisa A.; Block, Julie; Byrd-Bredbenner, Carol; Chan, Edmond S.; Eichenfield, Lawrence F.; Fleischer, David M.; Fuchs, George J.; Furuta, Glenn T.; Greenhawt, Matthew J.; Gupta, Ruchi S.; Habich, Michele; Jones, Stacie M.; Keaton, Kari; Muraro, Antonella; Plaut, Marshall; Rosenwasser, Lanny J.; Rotrosen, Daniel; Sampson, Hugh A.; Schneider, Lynda C.; Sicherer, Scott H.; Sidbury, Robert; Spergel, Jonathan; Stukus, David R.; Venter, Carina; Boyce, Joshua A.

    2016-01-01

    Background Food allergy is an important public health problem because it affects children and adults, it may be severe and even life-threatening, and it may be increasing in prevalence. Beginning in 2008, the National Institute of Allergy and Infectious Diseases (NIAID), working with other organizations and advocacy groups, led the development of the first clinical guidelines for the diagnosis and management of food allergy. A recent landmark clinical trial and other emerging data suggest that peanut allergy can be prevented through introduction of peanut-containing foods beginning in infancy. Objectives Prompted by these findings, along with 25 professional organizations, federal agencies, and patient advocacy groups, NIAID facilitated development of Addendum Guidelines to specifically address the prevention of peanut allergy. Results The Addendum provides three separate guidelines for infants at various risk levels for development of peanut allergy and is intended for use by a wide variety of health care providers. Topics addressed include the definition of risk categories, appropriate use of testing (specific IgE, skin prick testing, and oral food challenge) and the timing and approaches for introduction of peanut-containing foods in the health care provider’s office or at home. The Addendum Guidelines provide the background, rationale, and strength of evidence for each recommendation. Conclusions Guidelines have been developed for early introduction of peanut-containing foods into the diets of infants at various risk levels for peanut allergy. PMID:28065278

  4. The storage of liquid high level waste at BNFL, Sellafield. Addendum to February 2000 report

    International Nuclear Information System (INIS)

    2001-08-01

    On 18 February 2000 the Health and Safety Executive (HSE) published a report on the work of its Nuclear Installations Inspectorate (NIl) in regulating the storage of liquid high level waste at the BNFL Sellafield site. Within the report NIl gave two undertakings. One was to publish an addendum around 1 year later covering its assessment of the new safety case for the storage plant and the second was to publish a further addendum when progress had been made with options studies for reducing the stocks of liquid high level waste (HLW), also referred to as highly active liquor (HAL), to a buffer level. A progress report was published in February 2001 which included a summary of the assessment of the new safety case and NIl's regulatory action to enforce liquid HLW stock reductions. This addendum provides a more detailed update on the position reached based on consideration of BNFL's responses to the recommendations from the February 2000 HLW report since its publication. It embodies the two addenda referred to above integrated into a single document for publication

  5. Addendum 1 Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Vefa Yucel

    2001-01-01

    A disposal authorization statement (DAS) was issued by the U.S. Department of Energy/Headquarters (DOE/HQ) on December 5, 2000, authorizing the DOE's National Nuclear Security Administration Nevada Operations Office to continue the operation of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site for the disposal of low-level waste and mixed low-level waste. Prior to the issuance of the DAS, the Low-Level Waste Disposal Facility Federal Review Group (LFRG) had conducted reviews of the performance assessment (PA) and the composite analysis (CA) for the Area 5 RWMS, in accordance with the requirements of the DOE Radioactive Waste Management Order DOE O 435.1. A brief history of the reviews is as follows. (The reviews were conducted by independent review teams chartered by the LFRG; the review findings and recommendations were issued in review team reports to the LFRG.) The LFRG accepted the initial PA, with conditions, on August 30, 1996. Revision 2.1 to the PA was issued in January 1998, implementing the conditions of acceptance of the 1996 PA. The LFRG reviewed Revision 2.1 as part of the Area 5 RWMS CA review during 2000, and found it acceptable. The CA and the Supplemental Information provided in response to issues identified during the initial review of the CA were accepted by the LFRG. The Supplemental Information (including the responses to four key issues) is included in the Review Team Report to the LFRG, which recommends that it be incorporated into the CA and issued to all known holders of the CA. The Area 5 RWMS DAS requires that the Supplemental Information generated during the DOE/HQ review of the CA be incorporated into the CA within one year of the date of issuance of the DAS. This report, the first addendum to the Area 5 CA, is prepared to fulfill that requirement. The Supplemental Information includes the following: Issues Identified in the Review Team Report; Crosswalk Presentation; and Maintaining Doses As Low As Reasonably

  6. Origins of eponymous orthopaedic equipment.

    Science.gov (United States)

    Meals, Clifton; Wang, Jeffrey

    2010-06-01

    Orthopaedists make great use of eponymous equipment, however the origins of these tools are unknown to many users. This history enriches, enlightens, and enhances surgical education, and may inspire modern innovation. We explored the origins of common and eponymous orthopaedic equipment. We selected pieces of equipment named for their inventors and in the broadest use by modern orthopaedists. We do not describe specialized orthopaedic implants and instruments owing to the overwhelming number of these devices. The history of this equipment reflects the coevolution of orthopaedics and battlefield medicine. Additionally, these stories evidence the primacy of elegant design and suggest that innovation is often a process of revision and refinement rather than sudden inspiration. Their history exposes surgical innovators as brilliant, lucky, hardworking, and sometimes odd. These stories amuse, enlighten, and may inspire modern orthopaedists to develop creative solutions of their own. The rich history of the field's eponymous instruments informs an ongoing tradition of innovation in orthopaedics.

  7. Life Cycle Inventory (LCI) Data-Treatment Chemicals, Construction Materials, Transportation, On-site Equipment, and other Processes for Use in Spreadsheets for Environmental Footprint Analysis (SEFA): Revised Addition

    Science.gov (United States)

    This report estimates environmental emission factors (EmF) for key chemicals, construction and treatment materials, transportation/on-site equipment, and other processes used at remediation sites. The basis for chemical, construction, and treatment material EmFs is life cycle inv...

  8. Systems engineering functions and requirements for the Hanford cleanup mission. First issue, Addendum 2

    Energy Technology Data Exchange (ETDEWEB)

    Holmes, J.J.

    1994-01-01

    This addendum provides the technical detail of a systems engineering functional analysis for the Hanford cleanup mission. Details of the mission analysis including mission statement, scope, problem statement, initial state definition, and final state definition are provided in the parent document. The functional analysis consists of Input Computer Automated Manufacturing Definition (IDEFO) diagrams an definitions, which will be understood by systems engineers, but which may be difficult for others to comprehend. For a more complete explanation of this work, refer to the parent document. The analysis covers the total Hanford cleanup mission including the decomposition levels at which the various Hanford programs or integrated activities are encountered.

  9. Addendum to foundations of multidimensional wave field signal theory: Gaussian source function

    Directory of Open Access Journals (Sweden)

    Natalie Baddour

    2018-02-01

    Full Text Available Many important physical phenomena are described by wave or diffusion-wave type equations. Recent work has shown that a transform domain signal description from linear system theory can give meaningful insight to multi-dimensional wave fields. In N. Baddour [AIP Adv. 1, 022120 (2011], certain results were derived that are mathematically useful for the inversion of multi-dimensional Fourier transforms, but more importantly provide useful insight into how source functions are related to the resulting wave field. In this short addendum to that work, it is shown that these results can be applied with a Gaussian source function, which is often useful for modelling various physical phenomena.

  10. Addendum to foundations of multidimensional wave field signal theory: Gaussian source function

    Science.gov (United States)

    Baddour, Natalie

    2018-02-01

    Many important physical phenomena are described by wave or diffusion-wave type equations. Recent work has shown that a transform domain signal description from linear system theory can give meaningful insight to multi-dimensional wave fields. In N. Baddour [AIP Adv. 1, 022120 (2011)], certain results were derived that are mathematically useful for the inversion of multi-dimensional Fourier transforms, but more importantly provide useful insight into how source functions are related to the resulting wave field. In this short addendum to that work, it is shown that these results can be applied with a Gaussian source function, which is often useful for modelling various physical phenomena.

  11. 78 FR 66040 - 30-Day Notice of Proposed Information Collection: HUD-Owned Real Estate-Sales Contract and Addendums

    Science.gov (United States)

    2013-11-04

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5683-N-91] 30-Day Notice of Proposed Information Collection: HUD-Owned Real Estate--Sales Contract and Addendums AGENCY: Office of the Chief... published a 30 day notice of proposed information collection entitled HUD-Owned Real Estate-Sales Contract...

  12. 78 FR 76889 - Proposed Addendum to the Interagency Policy Statement on Income Tax Allocation in a Holding...

    Science.gov (United States)

    2013-12-19

    .... Please use the title ``Proposed Addendum to the Interagency Policy Statement on Income Tax Allocation in... to the Interagency Policy Statement on Income Tax Allocation in a Holding Company Structure'' to... for the Institution. Any tax refund attributable to income earned, taxes paid, and losses incurred by...

  13. Technical Review Report for the Model 9977 Safety Analysis Report for Packaging Addendum 1 Justification for DNDO Contents

    Energy Technology Data Exchange (ETDEWEB)

    West, M H

    2008-12-17

    The Model 9977 Package is currently certified for Content Envelope C.1, {sup 238}Pu Heat Sources, either in Radioisotope Thermoelectric Generator (RTG), or in Food-Pack Can configurations, under Certificate of Compliance (CoC) Certificate Number 9977 and Package Identification Number USA/9977/B(M)F-96 (DOE). Addendum 1, Justification for DNDO Contents,--the Submittal--supplements Revision 2 of the Safety Analysis Report for Packaging for the Model 9977 Package. The Submittal adds five new contents to the Model 9977 Package, Content Envelopes, AC.1 through AC.5. The Content Envelopes are neptunium metal, the beryllium-reflected plutonium ball (BeRP Ball), plutonium/uranium metal, plutonium/uranium metal with enhanced wt% {sup 240}Pu (to 50 wt%), and uranium metal. The last three Content Envelopes are stabilized to DOE-STD-3013. These Content Envelopes will be shipped to the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), where they will reside, and, hence, to off-site locations in support of the Department of Homeland Security (DHS) Domestic Nuclear Detection Office (DNDO). The new certificate will apply to a limited number of Model 9977 Packages. At the same time, the Submittal requests an extension of the periodic maintenance requirements from one (1) year to up to five (5) years using Radio-Frequency Identification (RFID) temperature-monitoring systems to measure the ambient storage temperature in order to ensure that the temperature of the Viton{reg_sign} O-rings for the 6-inch Containment Vessel (6CV) remain less than 200 F. The RFIDs have been developed by Argonne National Laboratory. An on-going surveillance program at the K-Area Materials Storage (KAMS) facility at the Savannah River Site, and an on-going examination of Viton{reg_sign} O-rings from mock Primary Containment Vessels (PCVs) at Savannah River National Laboratory (SRNL) provide the technical justification for the extension of the periodic maintenance interval. Where extended

  14. Quality Space and Launch Requirements, Addendum to AS9100C

    Science.gov (United States)

    2015-05-08

    Laboratories and Measuring and Test Equipment – General Requirements (1994) ISO 9001:2008 Quality management systems – Requirements (2008) ISO / IEC ...understood that not all suppliers may be compliant to AS9100 or perhaps even to ISO 9001. Section 7 provides requirements for selecting and monitoring... 17025 :2005 General requirements for the competence of testing and calibration laboratories MIL-STD-45662A Calibration Systems Requirements (Cancelled 27

  15. Final environmental statement. Final addendum to Part II: Manufacture of floating nuclear power plants by Offshore Power Systems. DOCKET-STN--50-437

    International Nuclear Information System (INIS)

    1978-06-01

    This Addendum to Part II of the Final Environmental Statement related to manufacture of floating nuclear power plants by Offshore Power Systems (OPS), NUREG-0056, issued September 1976, was prepared by the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation. The staff's basic evaluation is presented in NUREG-0056. The current Addendum provides further consideration of a number of topics discussed in NUREG-0056, particularly additional consideration of shore zone siting at estuarine and ocean regions. This Summary and Conclusions recapitulates and is cumulative for Part II of the FES and the current Addendum. Augmentations to the Summary and Conclusions presented in Part II of the FES and arising from the evaluations contained in this Addendum are italicized

  16. [Hydrotherapy equipment].

    Science.gov (United States)

    Tsibikov, V B; Ragozin, S I; Mikheeva, L V

    1985-01-01

    A flow-chart is developed demonstrating the relation between medical and prophylactic institutions within the organizational structure of the rehabilitation system and main types of rehabilitation procedures. In order to ascertain the priority in equipping rehabilitation services with adequate hardware the special priority criterion is introduced. The highest priority is assigned to balneotherapeutic and fangotherapeutic services. Based on the operation-by-operation analysis of clinical processes related to service and performance of balneologic procedures the preliminary set of clinical devices designed for baths, basins and showers in hospitals and rehabilitation departments is defined in a generalized form.

  17. Addendum to environmental monitoring plan Nevada Test Site and support facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    This 1992 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/1 0630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1992 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  18. Addendum to Environmental Monitoring Plan, Nevada Test Site and Support Facilities

    International Nuclear Information System (INIS)

    1993-11-01

    This 1993 Addendum to the ''Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,'' Report No. DOE/NV/10630-28 (EMP) applies to the US Department of Energy's (DOE's) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Operations Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1993 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards

  19. Cryogenic equipment

    International Nuclear Information System (INIS)

    Leger, L.; Javellaud, J.; Caro, C.; Gilguy, R.; Testard, O.

    1966-06-01

    The cryostats presented here were built from standard parts; this makes it possible to construct a great variety of apparatus at minimum cost. The liquid nitrogen and helium reservoirs were designed so as to reduce losses to a minimum, and so as to make the cryostats as autonomous as possible. The experimental enclosure which is generally placed in the lower part of the apparatus requires a separate study in every case. Furthermore, complete assemblies such as transfer rods, isolated traps and high vacuum valves, were designed with a similar regard for the economic aspects and for the need for standardization. This equipment thus satisfies a great variety of experimental needs; it is readily adaptable and the consumptions of helium and liquid nitrogen are very low. (authors) [fr

  20. A Guide for Equipping Industrial Arts Facilities.

    Science.gov (United States)

    American Industrial Arts Association, Washington, DC. Equipment Guide Committee.

    A guide for planning new and revising existing industrial arts facilities which gives a listing of tools and equipment recommended for each of the major areas of instruction (automotive and power mechanics, ceramics, drafting, electronics, elementary, general shop, graphic arts, metalworking, plastics, and woodworking). General descriptions and…

  1. 78 FR 71033 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Science.gov (United States)

    2013-11-27

    ... Reduction Act of 1995, PHMSA published a notice in the Federal Register of its intent to revise six forms... the failure of a piece of equipment is always due to a flaw in the equipment and never due to a...

  2. Medical Issues: Equipment

    Science.gov (United States)

    ... Information Packets Equipment Pool Living With SMA Medical Issues Palliative Breathing Orthopedics Nutrition Equipment Daily Life At ... curesma.org > support & care > living with sma > medical issues > equipment Equipment Individuals with SMA often require a ...

  3. Semiconductor Manufacturing equipment introduction

    International Nuclear Information System (INIS)

    Im, Jong Sun

    2001-02-01

    This book deals with semiconductor manufacturing equipment. It is comprised of nine chapters, which are manufacturing process of semiconductor device, history of semiconductor manufacturing equipment, kinds and role of semiconductor manufacturing equipment, construction and method of semiconductor manufacturing equipment, introduction of various semiconductor manufacturing equipment, spots of semiconductor manufacturing, technical elements of semiconductor manufacturing equipment, road map of technology of semiconductor manufacturing equipment and semiconductor manufacturing equipment in the 21st century.

  4. Work plan addendum for David Witherspoon, Inc., 901 Site Building Characterization, Knoxville, Tennessee

    International Nuclear Information System (INIS)

    1997-01-01

    This building characterization plan was developed as an addendum to the existing site characterization work plan documents, which are in Appendix B of the David Witherspoon, Inc., (DWI) preliminary remedial investigation (RI)/feasibility study (FS). All building characterization activities will be conducted in accordance with the rules of the Hazardous Substance Remedial Action Program under the direction of the Tennessee Department of Environment and Conservation, Division of Superfund (TN Rules 1200-1-3) and its implementing regulations. Additional rules of the state of Tennessee, Comprehensive Environmental Response, Compensation, and Liability Act of 1980, and the U.S. Environmental Protection Agency guidance were consulted during development of this plan. Activities at the DWI site were concerned with scrap metal processing and scrap metal resale

  5. Addendum 3 to CSAR 80-027, Use of calorimeter 109B for fissile material measurement

    International Nuclear Information System (INIS)

    Chiao, T.

    1994-01-01

    This modification to the Plutonium Finishing Plant (PFP) calorimeter system involves removing current calorimeter No. 3 from the water bath and replacing it with a calorimeter that can accommodate larger diameter items (an oversize can). The inside diameters of both the sample and the reference cells will be increased to 5.835 inches at the top opening and to 5.22 inches at the bottom, the 8 inch high measurement zone. This Addendum 3 to Criticality Safety Analysis Report 80-027 examines criticality safety during the use of the modified calorimeter (Calorimeter 109B) with enlarged cell tube diameters to assure that an adequate margin of subcriticality is maintained for all normal and contingency conditions

  6. Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

  7. Addendum to Technical Proposal: A Facility to Search for Hidden Particles (SHiP) at the CERN SPS

    CERN Document Server

    SHiP Collaboration

    2015-01-01

    With the Technical Proposal submitted to the SPSC committee in April 2015, the SHiP collaboration declared its interest in proceeding towards a Comprehensive Design Study phase with the aim of preparing for the Technical Design Reports pending an approval by the CERN committees. Following the recommendation by the SPSC, it has been decided to complement the TP with this addendum that provides an update of the key aspects for the review of the SHiP project.

  8. Maintenance program guidelines for programmatic equipment

    International Nuclear Information System (INIS)

    1994-11-01

    The Division Directors at Lawrence Berkeley Laboratory are responsible for implementing a maintenance program for research equipment (also referred to as programmatic equipment) assigned to them. The program must allow maintenance to be accomplished in a manner that promotes operational safety, environmental protection and compliance, and cost effectiveness; that preserves the intended functions of the facilities and equipment; and that supports the programmatic mission of the Laboratory. Programmatic equipment -- such as accelerators, lasers, radiation detection equipment, and glove boxes -- is dedicated specifically to research. Installed equipment, by contrast, includes the mechanical and electrical systems installed as part of basic building construction, equipment essential to the normal functioning of the facility and its intended use. Examples of installed equipment are heating, ventilating, and air conditioning systems; elevators; and communications systems. The LBL Operating and Assurance Program Plan (PUB-3111, Revision 4) requires that a maintenance program be prepared for programmatic equipment and defines the basic maintenance program elements. Such a program of regular, documented maintenance is vital to the safety and quality of research activities. As a part of that support, this document offers guidance to Laboratory organizations for developing their maintenance programs. It clarifies the maintenance requirements of the Operating and Assurance Program (OAP) and presents an approach that, while not the only possibility, can be expected to produce an effective maintenance program for research equipment belonging to the Laboratory's organizations

  9. Monitoring well plugging and abandonment plan, Y-12 Plant, Oak Ridge, Tennessee (revised)

    International Nuclear Information System (INIS)

    1997-05-01

    Plugging and abandonment (P ampersand A) of defunct groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP) (AJA Technical Services, Inc. 1996). This document is the revised groundwater monitoring well P ampersand A plan for the U.S. Department of Energy (DOE) Y-12 Plant located in Oak Ridge, Tennessee. This plan describes the systematic approach employed by Y-12 Plant GWPP to identify wells that require P ampersand A, the technical methods employed to perform P ampersand A activities, and administrative requirements. Original documentation for Y-12 Plant GWPP groundwater monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A schedule be maintained. Wells are added to this list by issuance of both a P ampersand A request and a P ampersand A addendum to the schedule. The current Updated Subsurface Data Base includes a single mechanism to track the status of monitoring wells. In addition, rapid growth of the groundwater monitoring network and new regulatory requirements have resulted in constant changes to the status of wells. As a result, a streamlined mechanism to identify and track monitoring wells scheduled for P ampersand A has been developed and the plan revised to formalize the new business practices

  10. CSAR 81-001 addendum 2: Use of a plexiglass contamination barrier in HC-227-T

    International Nuclear Information System (INIS)

    Chiao, T.

    1994-01-01

    Plutonium Finish Plant (PFP) Engineering requested a criticality safety evaluation (Appendix 1) to support a revision of Criticality Prevention Specification CPS-Z-165-80601 allowing a plexiglass enclosure (PGE) to be placed inside the HC-227T hood as a contamination barrier. The HC-227T hood is the receiving/transfer enclosure for Pu nitrate solution contained in Product Removal containers (PR Cans), L10 Containers (L10, Fl-10, 10 L) or L-3 Containers. Within the HC-227T, a 1.349 square meter (15 square foot) enclosure, PGE, has been created to provide contamination control around the weighing scale. Two or more standard criticality drains shall be installed on this enclosure prior to beneficial usage. The evaluation considered the normal process, spillage scenarios, waste/container accumulations within the enclosure, and interactions of Pu within the enclosure as well as other containers external to the enclosure. The results from the criticality safety analysis by CRA shows that such as contamination barrier can be placed inside the HC-227T Hood if the PGE is equipped with adequate criticality drains. In addition, other limits as well as administrative controls listed in CPS-Z-165-80601 Rev./Mod. B/0 and CPS-Z-165-80010 Rev./Mod. C/1 shall also apply

  11. Selection of equipment for equipment qualification

    International Nuclear Information System (INIS)

    Torr, K.G.

    1989-01-01

    This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

  12. Operation and maintenance manual addendum to Westinghouse OMM-051-00-005 for intermediate-size inducer pump (ISIP) Model 266

    International Nuclear Information System (INIS)

    1979-01-01

    This Addendum A to the Westinghouse Operation and Maintenance Manual OMM-051-00-005 contains additions, changes and deletions that modify data for the Liquid Metal Coolant Pump, Model LMP-1 to data applicable to the Rockwell International Intermediate-Size Inducer Pump (ISIP), Model 266. The major modifications on the ISIP are the new impeller/inducer assembly, diffuser vanes and new securing hardware. The paragraphs affected by Addendum A use the numbering system used in OMM-051-00-005 except each paragraph number is prefixed with an A preceding the paragraph number signifying that the paragraph is changed to conform with the ISIP configuration. Paragraphs within OMM-051-00-005 not identified in Addendum A remain unchanged with the data still valid and useable

  13. Addendum report of the JHPS expert committee on radiation protection of the lens of the eye (1). Eye lens dosimetry R and D, and radiation management and estimated eye-lens exposure for workers in Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Akahane, Keiichi; Tatsuzaki, Hideo; Iimoto, Takeshi; Ichiji, Takeshi; Hamada, Nobuyuki; Iwai, Satoshi; Ohguchi, Hiroyuki; Ohno, Kazuko; Katoh, Masahiro; Kurosawa, Tadahiro; Kawaura, Chiyo; Tsujimura, Norio; Hayashida, Toshiyuki; Hotta, Yutaka; Yamasaki, Tadashi; Yokoyama, Sumi

    2015-01-01

    The Expert Committee on Radiation Protection of the Lens of the Eye was established under the Japan Health Physics Society in April, 2013 (completed, March, 2015). The Committee looked at new/revised documents and standards related to the eye lens published by international organizations such as the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU). The Committee also examined recent and previous studies related to eye-lens radiation exposure and dosimetry in Japan. These findings were published in this journal as the Interim Report of the Committee. Since then, the Committee expanded its activity to give an overview the current progress of eye-lens dosimetry R and D at the National Institute of Advanced Industrial Science and Technology, along with research related to radiation management and estimated eye-lens exposure of Japanese nuclear-power-plant workers (including those at Fukushima Daiichi Nuclear Power Plant) for publishing an addendum Committee report. These additional findings are reported here. (author)

  14. Loosening After Acetabular Revision

    DEFF Research Database (Denmark)

    Beckmann, Nicholas A.; Weiss, Stefan; Klotz, Matthias C.M.

    2014-01-01

    The best method of revision acetabular arthroplasty remains unclear. Consequently, we reviewed the literature on the treatment of revision acetabular arthroplasty using revision rings (1541 cases; mean follow-up (FU) 5.7 years) and Trabecular Metal, or TM, implants (1959 cases; mean FU 3.7 years...

  15. Radiation therapy sources, equipment and installations

    International Nuclear Information System (INIS)

    2011-03-01

    The safety code for Telegamma Therapy Equipment and Installations, (AERB/SC/MED-1) and safety code for Brachytherapy Sources, Equipment and Installations, (AERB/SC/MED-3) were issued by AERB in 1986 and 1988 respectively. These codes specified mandatory requirements for radiation therapy facilities, covering the entire spectrum of operations ranging from the setting up of a facility to its ultimate decommissioning, including procedures to be followed during emergency situations. The codes also stipulated requirements of personnel and their responsibilities. With the advent of new techniques and equipment such as 3D-conformal radiation therapy, intensity modulated radiation therapy, image guided radiation therapy, treatment planning system, stereotactic radiosurgery, stereotactic radiotherapy, portal imaging, integrated brachytherapy and endovascular brachytherapy during the last two decades, AERB desires that these codes be revised and merged into a single code titled Radiation Therapy Sources, Equipment, and Installations

  16. Characterization equipment essential/support drawing plan

    International Nuclear Information System (INIS)

    WILSON, G.W.

    1999-01-01

    The purpose of this document is to list the Characterization equipment drawings that are classified as Essential Drawings and Support Drawings. Essential Drawings: Are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment (HNF 1997a). Support Drawings: Are those drawings identified by facility staff that further describe the design details of structures, systems, or components shown on essential drawings. (HNF 1997a) The Characterization equipment drawings identified in this report are deemed essential drawings as defined in HNF-PRO-242, Engineering Drawing Requirements (HNF 1997a). These drawings will be prepared, revised, and maintained per HNF-PRO-440, Engineering Document Change Control (HNF 1997b). All other Characterization equipment drawings not identified in this document will be considered General drawings until the Characterization Equipment Drawing Evaluation Report (Wilson 1998) is updated during fiscal year 1999. Trucks 1 and 2 drawings are not included in this revision of the essential drawing list due to uncertainty about future use

  17. Dredging: An Annotated Bibliography on Operations, Equipment, and Processes. Revision.

    Science.gov (United States)

    1982-03-01

    aggregate mining. 0006 APGAR , W. J. and BASCO, D. R. 1973 (Oct). "An Experimental and Theoretical Study of the Flow Field Surrounding a Suction Pipe...modes. Sub-systems designed in way that in case of emergency they can operate independently, or, if necessary, can be over- ruled by manual control...0442 VANONI, V. A. (Editor). 1975. Sedimentation Engineering, Manuals and Reports on Engineering Practice No. 54, ASCE, New York. Contents: Nature of

  18. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    Energy Technology Data Exchange (ETDEWEB)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI.

  19. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    International Nuclear Information System (INIS)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S ampersand A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S ampersand A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI

  20. NASA satellite communications application research, phase 2 addendum. Efficient high power, solid state amplifier for EHF communications

    Science.gov (United States)

    Benet, James

    1994-01-01

    This document is an addendum to the NASA Satellite Communications Application Research (SCAR) Phase 2 Final Report, 'Efficient High Power, Solid State Amplifier for EHF Communications.' This report describes the work performed from 1 August 1993 to 11 March 1994, under contract number NASW-4513. During this reporting period an array of transistor amplifiers was repaired by replacing all MMIC amplifier chips. The amplifier array was then tested using three different feedhorn configurations. Descriptions, procedures, and results of this testing are presented in this report, and conclusions are drawn based on the test results obtained.

  1. The Economic and Workforce Development Program (ED>Net) Annual Report, 2001-02 [and] Addendum to FY 01-02 Annual Report.

    Science.gov (United States)

    California Community Colleges, Sacramento. Economic Development Coordination Network (EDNet).

    This document contains an annual report and its addendum from the Economic and Workforce Development Program of California Community Colleges. The annual report provides an overview of the Program's evaluation processes, regional centers, short-term projects, legislation, strategic plan, etc. It also provides vital facts about the program such as…

  2. The detection and settlement of VAT fraud in four countries : Addendum to the report value-added tax fraud in the European Union

    NARCIS (Netherlands)

    Aronowitz, A.A.; Laagland, D.C.G.; Paulides, G.

    1996-01-01

    This addendum to the report 'Value-added tax fraud in the European Union' gives additional information on the detection and settlement of VAT fraud in Belgium, Germany, the United Kingdom and the Netherlands. See link to the report at: More information.

  3. Addendum to "Increasing Early Childhood Educators' Use of Communication-Facilitating and Language-Modelling Strategies: Brief Speech and Language Therapy Training"

    Science.gov (United States)

    McDonald, David; Proctor, Penny; Gill, Wendy; Heaven, Sue; Marr, Jane; Young, Jane

    2015-01-01

    The purpose of this addendum is to include within our discussion the findings of Girolametto et al. (2007), a randomized controlled trial of Teacher Talk training, an adapted version of Learning Language and Loving It (LLLI) (Weitzman and Greenberg, 2002). Teacher Talk does not include the coaching and video feedback elements of LLLI. Girolametto…

  4. Super-GCA connection with tensionless strings: Addendum to “Super-GCA from N=(2,2 super-Virasoro” [Phys. Lett. B 754 (2016 195–200

    Directory of Open Access Journals (Sweden)

    Ipsita Mandal

    2016-09-01

    Full Text Available In this addendum, we consider the connection between certain 2d super-GCA, obtained from the parametric contractions of 2d SCFTs, which can describe the constraint algebra of null spinning strings.

  5. Shipboard and laboratory equipment

    Digital Repository Service at National Institute of Oceanography (India)

    Shyamprasad, M.; Ramaswamy, V.

    The polymetallic nodules occur at an average depth of 4500 m. Adequate equipment and techniques are required for the exploration at such depths. Shipboard and various laboratory equipments for the sampling of polymetallic nodules is described...

  6. Remote handling equipment

    International Nuclear Information System (INIS)

    Clement, G.

    1984-01-01

    After a definition of intervention, problems encountered for working in an adverse environment are briefly analyzed for development of various remote handling equipments. Some examples of existing equipments are given [fr

  7. Exercise Equipment: Neutral Buoyancy

    Science.gov (United States)

    Shackelford, Linda; Valle, Paul

    2016-01-01

    Load Bearing Equipment for Neutral Buoyancy (LBE-NB) is an exercise frame that holds two exercising subjects in position as they apply counter forces to each other for lower extremity and spine loading resistance exercises. Resistance exercise prevents bone loss on ISS, but the ISS equipment is too massive for use in exploration craft. Integrating the human into the load directing, load generating, and motion control functions of the exercise equipment generates safe exercise loads with less equipment mass and volume.

  8. BP volume reduction equipment

    International Nuclear Information System (INIS)

    Kitamura, Yoshinori; Muroo, Yoji; Hamanaka, Isao

    2003-01-01

    A new type of burnable poison (BP) volume reduction system is currently being developed. Many BP rods, a subcomponent of spent fuel assemblies are discharged from nuclear power reactors. This new system reduces the overall volume of BP rods. The main system consists of BP rod cutting equipment, equipment for the recovery of BP cut pieces, and special transport equipment for the cut rods. The equipment is all operated by hydraulic press cylinders in water to reduce operator exposure to radioactivity. (author)

  9. Anxiety Disorders Interview Schedule – Autism Addendum: Reliability and Validity in Children with Autism Spectrum Disorder

    Science.gov (United States)

    Kerns, Connor Morrow; Renno, Patricia; Kendall, Philip C.; Wood, Jeffrey J.; Storch, Eric A.

    2017-01-01

    Objective Assessing anxiety in autism spectrum disorder (ASD) is inherently challenging due to overlapping (e.g., social avoidance) and ambiguous symptoms (e.g., fears of change). An ASD addendum to the Anxiety Disorders Interview Schedule–Child/Parent, Parent Version (ADIS/ASA) was developed to provide a systematic approach for differentiating traditional anxiety disorders from symptoms of ASD and more ambiguous, ASD-related anxiety symptoms. Method Inter-rater reliability and convergent and discriminant validity were examined in a sample of 69 youth with ASD (8–13 years, 75% male, IQ:68–143) seeking treatment for anxiety. The parents of participants completed the ADIS/ASA and a battery of behavioral measures. A second rater independently observed and scored recordings of the original interviews. Results Findings suggest reliable measurement of comorbid (ICC=0.85–0.98; κ =0.67–0.91) as well as ambiguous anxiety-like symptoms (ICC=0.87–95, κ=0.77–0.90) in children with ASD. Convergent and discriminant validity were supported for the traditional anxiety symptoms on the ADIS/ASA, whereas convergent and discriminant validity were partially supported for the ambiguous anxiety-like symptoms. Conclusions Results provide evidence for the reliability and validity of the ADIS/ASA as a measure of traditional anxiety categories in youth with ASD, with partial support for the validity of the ambiguous anxiety-like categories. Unlike other measures, the ADIS/ASA differentiates comorbid anxiety disorders from overlapping and ambiguous anxiety-like symptoms in ASD, allowing for more precise measurement and clinical conceptualization. Ambiguous anxiety-like symptoms appear phenomenologically distinct from comorbid anxiety disorders and may reflect either symptoms of ASD or a novel variant of anxiety in ASD. PMID:27925775

  10. Bibliocable. Revised Edition.

    Science.gov (United States)

    Cable Television Information Center, Washington, DC.

    This selective, annotated bibliography is a revision of the original published in 1972 (ED 071 402). Some 104 books, articles, and reports included here deal with access, applications, franchising, regulation, technology, and other aspects of cable television. The listings are of two types in each category. First are revisions of the original…

  11. Similarity principles for equipment qualification by experience

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1988-07-01

    A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data are available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to ultimate fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application of the procedures and verification of them are given for certain cases that can be approximated by a two degree of freedom simple primary/secondary system. Other examples are based on use of actual test data available from previous qualifications. Relationships of the developments with other previously-published methods are discussed. The developments are intended to elaborate on the rather broad revised guidelines developed by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. However, the results also contribute to filling a gap that exists between the IEEE 344 methodology and that previously developed by the Seismic Qualification Utilities Group. The relationship of the results to safety margin methodology is also discussed. (author)

  12. Electrical equipment qualification

    International Nuclear Information System (INIS)

    Farmer, W.S.

    1983-01-01

    Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

  13. Master Minimum Equipment List -

    Data.gov (United States)

    Department of Transportation — The AEG System is used to create, revise, approve, and distribute text of the MMEL and Flight Standard Board (FSB)/Type Rating Report. The MMEL specifies under what...

  14. Addendum to the corrective action plan for Underground Storage Tanks 1219-U, 1222-U, 2082-U, 2068-U at the Rust Garage Facility, Buildings 9720-15 and 9754-1: Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID number-sign 0-010117

    International Nuclear Information System (INIS)

    1994-01-01

    This document represents an addendum to the Corrective Action Plan (CAP) for underground storage tanks 1219-U, 2082-U, and 2068-U located at Buildings 9720-15 and 9754-1, Oak Ridge Y-12 Plant, Oak Ridge, TN. The site of the four underground storage tanks is commonly referred to as the Rust Garage Facility. The original CAP was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review in May 1992. During the time period after submission of the original CAP for the Rust Garage Facility, Y-12 Plant Underground Storage Tank (UST) Program personnel continued to evaluate improvements that would optimize resources and expedite the activities schedule presented in the original CAP. Based on these determinations, several revisions to the original corrective action process options for remediation of contaminated soils are proposed. The revised approach will involve excavation of the soils from the impacted areas, on-site thermal desorption of soil contaminants, and final disposition of the treated soils by backfilling into the subject site excavations. Based on evaluation of the corrective actions with regard to groundwater, remediation of groundwater under the Y-12 Plant CERCLA Program is proposed for the facility

  15. Space Heating Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Rafferty, Kevin D.

    1998-01-01

    The performance evaluation of space heating equipment for a geothermal application is generally considered from either of two perspectives: (a) selecting equipment for installation in new construction, or (b) evaluating the performance and retrofit requirements of an existing system. With regard to new construction, the procedure is relatively straightforward. Once the heating requirements are determined, the process need only involve the selection of appropriately sized hot water heating equipment based on the available water temperature. It is important to remember that space heating equipment for geothermal applications is the same equipment used in non-geothermal applications. What makes geothermal applications unique is that the equipment is generally applied at temperatures and flow rates that depart significantly from traditional heating system design. This chapter presents general considerations for the performance of heating equipment at non-standard temperature and flow conditions, retrofit of existing systems, and aspects of domestic hot water heating.

  16. Renewal of radiological equipment.

    Science.gov (United States)

    2014-10-01

    In this century, medical imaging is at the heart of medical practice. Besides providing fast and accurate diagnosis, advances in radiology equipment offer new and previously non-existing options for treatment guidance with quite low morbidity, resulting in the improvement of health outcomes and quality of life for the patients. Although rapid technological development created new medical imaging modalities and methods, the same progress speed resulted in accelerated technical and functional obsolescence of the same medical imaging equipment, consequently creating a need for renewal. Older equipment has a high risk of failures and breakdowns, which might cause delays in diagnosis and treatment of the patient, and safety problems both for the patient and the medical staff. The European Society of Radiology is promoting the use of up-to-date equipment, especially in the context of the EuroSafe Imaging Campaign, as the use of up-to-date equipment will improve quality and safety in medical imaging. Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or renewal. This plan should look forward a minimum of 5 years, with annual updates. Teaching points • Radiological equipment has a definite life cycle span, resulting in unavoidable breakdown and decrease or loss of image quality which renders equipment useless after a certain time period.• Equipment older than 10 years is no longer state-of-the art equipment and replacement is essential. Operating costs of older equipment will be high when compared with new equipment, and sometimes maintenance will be impossible if no spare parts are available.• Older equipment has a high risk of failure and breakdown, causing delays in diagnosis and treatment of the patient and safety problems both for the patient and the medical staff.• Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or replacement. This plan should look forward a

  17. RETRIEVAL EQUIPMENT DESCRIPTIONS

    International Nuclear Information System (INIS)

    J. Steinhoff

    1997-01-01

    The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) retrieval from the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. There are no quality assurance requirements or QA controls in this document. Retrieval under normal conditions is accomplished with the same fleet of equipment as is used for emplacement. Descriptions of equipment used for retrieval under normal conditions is found in Emplacement Equipment Descriptions, DI: BCAF00000-01717-5705-00002 (a document in progress). Equipment used for retrieval under abnormal conditions is addressed in this document and consists of the following: (1) Inclined Plane Hauler; (2) Bottom Lift Transporter; (3) Load Haul Dump (LHD) Loader; (4) Heavy Duty Forklift for Emplacement Drifts; (5) Covered Shuttle Car; (6) Multipurpose Vehicle; and (7) Scaler

  18. Annual report of the group for maintenance of electrical equipment

    International Nuclear Information System (INIS)

    Rajic, M.

    1965-01-01

    This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well [sr

  19. Medical equipment management

    CERN Document Server

    Willson, Keith; Tabakov, Slavik

    2013-01-01

    Know What to Expect When Managing Medical Equipment and Healthcare Technology in Your Organization As medical technology in clinical care becomes more complex, clinical professionals and support staff must know how to keep patients safe and equipment working in the clinical environment. Accessible to all healthcare professionals and managers, Medical Equipment Management presents an integrated approach to managing medical equipment in healthcare organizations. The book explains the underlying principles and requirements and raises awareness of what needs to be done and what questions to ask. I

  20. Data communication equipment

    International Nuclear Information System (INIS)

    Kim, Hak Seon; Lee, Sang Mok

    1998-02-01

    The contents of this book are introduction of data communication on definition, purpose and history, information terminal about data communication system and data transmission system, data transmit equipment of summary, transmission cable, data port, concentrator and front-end processor, audio communication equipment like phones, radio communication equipment of summary on foundation of electromagnetic waves, AM transmitter, AM receiver, FM receiver and FM transmitter, a satellite and mobile communication equipment such as earth station, TT and C and Cellular phone, video telephone and new media apparatus.

  1. Publishing and Revising Content

    Science.gov (United States)

    Editors and Webmasters can publish content without going through a workflow. Publishing times and dates can be set, and multiple pages can be published in bulk. Making an edit to published content created a revision.

  2. Letter of Map Revision

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — The National Flood Hazard Layer (NFHL) data incorporates all Digital Flood Insurance Rate Map(DFIRM) databases published by FEMA, and any Letters Of Map Revision...

  3. Measurement of environmental radiation exposure rates from Vernita, Hanford Reach, and Richland area shores. Addendum 1

    International Nuclear Information System (INIS)

    Cooper, A.T.

    1995-02-01

    Environmental radiation exposure rate measurements are taken on and around the Hanford Site for Pacific Northwest Laboratory's Hanford Site Surface Environmental Surveillance Project. In 1992, environmental radiation exposure rate measurements were taken from shoreline and island areas ranging from Vernita, along the Hanford Reach, down to the Richland Pumphouse. Measurements were taken primarily at locations known or expected to have elevated exposure rates as determined by examination of aerial photographs depicting radiation exposure measurements. Results from the 1992 survey indicated radiation exposure rates taken from the Hanford Reach area were elevated in comparison to the measurements taken from the Vernita area with ranges of 8 to 28 μR/hr and 4 to 11 μR/hr, respectively. In January 1994, additional shoreline radiation exposure rate measurements were taken from the Vernita, Hanford Reach, and Richland areas to determine the relationship of radiation exposure rates along the Richland area shores when compared to Vernita and Hanford Reach area exposure rates (measurements along the Richland area were not collected during the 1992 survey). This report discusses the 1994 results and is an addendum to the report that discussed the 1992 survey. An analysis of variance indicated a significant location interaction at a p-value of 0.0014. To determine differences between paried locations a post-hoc comparison of location means was performed on log transformed data using the Scheffacute e's F-test. This test indicated a significant difference between Hanford Reach and Richland area means with a mean difference of 0.075 /μR/hr and a p-value of 0.0014. No significant difference was found between Hanford Reach and Vernita area means: The mean difference was 0.031 μR/hr and the p-value was 0.3138. No significant difference was found between Vernita and Richland area means with a mean difference of 0.044 μR/hr and a p-value of 0.1155

  4. Cooling of electronic equipment

    DEFF Research Database (Denmark)

    A. Kristensen, Anders Schmidt

    2003-01-01

    Cooling of electronic equipment is studied. The design size of electronic equipment decrease causing the thermal density to increase. This affect the cooling which can cause for example failures of critical components due to overheating or thermal induced stresses. Initially a pin fin heat sink...

  5. Capital Equipment Replacement Decisions

    OpenAIRE

    Batterham, Robert L.; Fraser, K.I.

    1995-01-01

    This paper reviews the literature on the optimal replacement of capital equipment, especially farm machinery. It also considers the influence of taxation and capital rationing on replacement decisions. It concludes that special taxation provisions such as accelerated depreciation and investment allowances are unlikely to greatly influence farmers' capital equipment replacement decisions in Australia.

  6. Addendum Guidelines for the Prevention of Peanut Allergy in the United States: Report of the National Institute of Allergy and Infectious Diseases-Sponsored Expert Panel.

    Science.gov (United States)

    Togias, Alkis; Cooper, Susan F; Acebal, Maria L; Assa'ad, Amal; Baker, James R; Beck, Lisa A; Block, Julie; Byrd-Bredbenner, Carol; Chan, Edmond S; Eichenfield, Lawrence F; Fleischer, David M; Fuchs, George J; Furuta, Glenn T; Greenhawt, Matthew J; Gupta, Ruchi S; Habich, Michele; Jones, Stacie M; Keaton, Kari; Muraro, Antonella; Plaut, Marshall; Rosenwasser, Lanny J; Rotrosen, Daniel; Sampson, Hugh A; Schneider, Lynda C; Sicherer, Scott H; Sidbury, Robert; Spergel, Jonathan; Stukus, David R; Venter, Carina; Boyce, Joshua A

    Food allergy is an important public health problem because it affects children and adults, can be severe and even life-threatening, and may be increasing in prevalence. Beginning in 2008, the National Institute of Allergy and Infectious Diseases, working with other organizations and advocacy groups, led the development of the first clinical guidelines for the diagnosis and management of food allergy. A recent landmark clinical trial and other emerging data suggest that peanut allergy can be prevented through introduction of peanut-containing foods beginning in infancy. Prompted by these findings, along with 25 professional organizations, federal agencies, and patient advocacy groups, the National Institute of Allergy and Infectious Diseases facilitated development of addendum guidelines to specifically address the prevention of peanut allergy. The addendum provides 3 separate guidelines for infants at various risk levels for the development of peanut allergy and is intended for use by a wide variety of health care providers. Topics addressed include the definition of risk categories, appropriate use of testing (specific IgE measurement, skin prick tests, and oral food challenges), and the timing and approaches for introduction of peanut-containing foods in the health care provider's office or at home. The addendum guidelines provide the background, rationale, and strength of evidence for each recommendation. Guidelines have been developed for early introduction of peanut-containing foods into the diets of infants at various risk levels for peanut allergy. Published by Elsevier Inc.

  7. Acetabular Cup Revision.

    Science.gov (United States)

    Kim, Young-Ho

    2017-09-01

    The use of acetabular cup revision arthroplasty is on the rise as demands for total hip arthroplasty, improved life expectancies, and the need for individual activity increase. For an acetabular cup revision to be successful, the cup should gain stable fixation within the remaining supportive bone of the acetabulum. Since the patient's remaining supportive acetabular bone stock plays an important role in the success of revision, accurate classification of the degree of acetabular bone defect is necessary. The Paprosky classification system is most commonly used when determining the location and degree of acetabular bone loss. Common treatment options include: acetabular liner exchange, high hip center, oblong cup, trabecular metal cup with augment, bipolar cup, bulk structural graft, cemented cup, uncemented cup including jumbo cup, acetabular reinforcement device (cage), trabecular metal cup cage. The optimal treatment option is dependent upon the degree of the discontinuity, the amount of available bone stock and the likelihood of achieving stable fixation upon supportive host bone. To achieve successful acetabular cup revision, accurate evaluation of bone defect preoperatively and intraoperatively, proper choice of method of acetabular revision according to the evaluation of acetabular bone deficiency, proper technique to get primary stability of implant such as precise grafting technique, and stable fixation of implant are mandatory.

  8. HVAC systems and equipment

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, S.T. (Linford Air and Refrigeration Company, Oakland, CA (US))

    1990-02-01

    The author discusses the section of the ASHRAE Standard 90.1-1989 which addresses HVAC systems and equipment. New features of HVAC systems mandatory general requirements are described. New prescriptive requirements are detailed.

  9. Personal Protective Equipment

    National Research Council Canada - National Science Library

    1998-01-01

    ... of personal protective equipment A safety program for new employees is a necessary part of any orientation program An on-going safety program should be used to motivate employees to continue to use...

  10. Electronic equipment packaging technology

    CERN Document Server

    Ginsberg, Gerald L

    1992-01-01

    The last twenty years have seen major advances in the electronics industry. Perhaps the most significant aspect of these advances has been the significant role that electronic equipment plays in almost all product markets. Even though electronic equipment is used in a broad base of applications, many future applications have yet to be conceived. This versatility of electron­ ics has been brought about primarily by the significant advances that have been made in integrated circuit technology. The electronic product user is rarely aware of the integrated circuits within the equipment. However, the user is often very aware of the size, weight, mod­ ularity, maintainability, aesthetics, and human interface features of the product. In fact, these are aspects of the products that often are instrumental in deter­ mining its success or failure in the marketplace. Optimizing these and other product features is the primary role of Electronic Equipment Packaging Technology. As the electronics industry continues to pr...

  11. CV equipment responsibilities

    CERN Document Server

    Pirollet, B

    2008-01-01

    This document describes the limits of the responsibilities of the TS/CV for fire fighting equipment at the LHC. The various interfaces, providers and users of the water supply systems and clean water raising systems are described.

  12. Equipment for hydraulic testing

    International Nuclear Information System (INIS)

    Jacobsson, L.; Norlander, H.

    1981-07-01

    Hydraulic testing in boreholes is one major task of the hydrogeological program in the Stripa Project. A new testing equipment for this purpose was constructed. It consists of a downhole part and a surface part. The downhole part consists of two packers enclosing two test-sections when inflated; one between the packers and one between the bottom packer and the bottom of the borehole. A probe for downhole electronics is also included in the downhole equipment together with electrical cable and nylon tubing. In order to perform shut-in and pulse tests with high accuracy a surface controlled downhole valve was constructed. The surface equipment consists of the data acquisition system, transducer amplifier and surface gauges. In the report detailed descriptions of each component in the whole testing equipment are given. (Auth.)

  13. Reply to the SPSC questions on Addendum CERN-SPSC-2018-008 entitled Study of Hadron-Nucleus and Nucleus-Nucleus Collisions at the CERN SPS: Early Post-LS2 Measurements and Future Plans

    CERN Document Server

    Aduszkiewicz, A

    2018-01-01

    This document presents answers of the NA61/SHINE Collaborations to the SPSC questions on the addendum CERN-SPSC-2018-008 (referred to as ''Addendum'') to the NA61/SHINE proposal. Addendum requests an extension of the NA61/SHINE measurements beyond the Long Shutdown 2 and approval of the first physics data taking in 2022. The SPSC requested NA61/SHINE to consider a possibility to start the first physics data taking in 2021. NA61/SHINE concludes that this is possible and requests beam time in 2021 for detector commissioning and tests as well as for data taking with hadron (for neutrino physics) and Pb (for open charm measurements in Pb+Pb collisions) beams. The critical issue is timely flow of financial resources needed for the hardware of the detector upgrade.

  14. Revision of Pachycentria (Melastomataceae)

    NARCIS (Netherlands)

    Clausing, Gudrun

    2000-01-01

    A revision of Pachycentria Blume, which includes the monotypic Pogonanthera Blume, is presented. Pachycentria comprises eight species and one subspecies. Two species, P. vogelkopensis and P. hanseniana, are newly described. The genus is distinguished from other genera in the Medinillinae by a small

  15. Revision of Oxandra (Annonaceae)

    NARCIS (Netherlands)

    Junikka, L.; Maas, P.J.M.; Maas-van de Kamer, H.; Westra, L.Y.Th.

    2016-01-01

    A taxonomic revision is given of the Neotropical genus Oxandra (Annonaceae). Within the genus 27 species are recognized, 4 of which are new to science. Most of the species are occurring in tropical South America, whereas a few (6) are found in Mexico and Central America and two in the West Indies

  16. Revision without ordinals

    NARCIS (Netherlands)

    Rivello, Edoardo

    2013-01-01

    We show that Herzberger’s and Gupta’s revision theories of truth can be recast in purely inductive terms, without any appeal neither to the transfinite ordinal numbers nor to the axiom of Choice. The result is presented in an abstract and general setting, emphasising both its validity for a wide

  17. Revising and editing for translators

    CERN Document Server

    Mossop, Brian

    2014-01-01

    Revising and Editing for Translators provides guidance and learning materials for translation students learning to edit texts written by others, and professional translators wishing to improve their self-revision ability or learning to revise the work of others. Editing is understood as making corrections and improvements to texts, with particular attention to tailoring them to the given readership. Revising is this same task applied to draft translations. The linguistic work of editors and revisers is related to the professional situations in which they work. Mossop offers in-depth coverage of a wide range of topics, including copyediting, style editing, structural editing, checking for consistency, revising procedures and principles, and translation quality assessment. This third edition provides extended coverage of computer aids for revisers, and of the different degrees of revision suited to different texts. The inclusion of suggested activities and exercises, numerous real-world examples, a proposed gra...

  18. Equipment abnormality monitoring device

    International Nuclear Information System (INIS)

    Ando, Yasumasa

    1991-01-01

    When an operator hears sounds in a plantsite, the operator compares normal sounds of equipment which he previously heard and remembered with sounds he actually hears, to judge if they are normal or abnormal. According to the method, there is a worry that abnormal conditions can not be appropriately judged in a case where the number of objective equipments is increased and in a case that the sounds are changed gradually slightly. Then, the device of the present invention comprises a plurality of monitors for monitoring the operation sound of equipments, a recording/reproducing device for recording and reproducing the signals, a selection device for selecting the reproducing signals among the recorded signals, an acoustic device for converting the signals to sounds, a switching device for switching the signals to be transmitted to the acoustic device between to signals of the monitor and the recording/reproducing signals. The abnormality of the equipments can be determined easily by comparing the sounds representing the operation conditions of equipments for controlling the plant operation and the sounds recorded in their normal conditions. (N.H.)

  19. Prioritizing equipment for replacement.

    Science.gov (United States)

    Capuano, Mike

    2010-01-01

    It is suggested that clinical engineers take the lead in formulating evaluation processes to recommend equipment replacement. Their skill, knowledge, and experience, combined with access to equipment databases, make them a logical choice. Based on ideas from Fennigkoh's scheme, elements such as age, vendor support, accumulated maintenance cost, and function/risk were used.6 Other more subjective criteria such as cost benefits and efficacy of newer technology were not used. The element of downtime was also omitted due to the data element not being available. The resulting Periop Master Equipment List and its rationale was presented to the Perioperative Services Program Council. They deemed the criteria to be robust and provided overwhelming acceptance of the list. It was quickly put to use to estimate required capital funding, justify items already thought to need replacement, and identify high-priority ranked items for replacement. Incorporating prioritization criteria into an existing equipment database would be ideal. Some commercially available systems do have the basic elements of this. Maintaining replacement data can be labor-intensive regardless of the method used. There is usually little time to perform the tasks necessary for prioritizing equipment. However, where appropriate, a clinical engineering department might be able to conduct such an exercise as shown in the following case study.

  20. Radioactive decontamination of equipment

    International Nuclear Information System (INIS)

    1982-03-01

    After a recall of some definitions relating to decontamination techniques and of the regulation into effect, the principles to be respected to arrange rationally work zones are quoted while insisting more particularly on the types of coatings which facilitate maintenance operations and the dismantling of these installations. Then, the processes and equipments to use in decontamination units for routine or particular operations are described; the list of recommended chemical products to decontaminate the equipment is given. The influence of these treatments on the state and the duration of life of equipments is studied, and some perfectible methods are quoted. In the appendix, are given: the limits of surface contamination accepted in the centers; a standard project which defines the criteria of admissible residual contamination in wastes considered as cold wastes; some remarks on the interest that certain special ventilation and air curtain devices for the protection of operators working on apparatus generating contaminated dusts [fr

  1. Reviews Opera: Doctor Atomic DVD: Doctor Atomic Equipment: Digital stopclock with external trigger Book: I Cyborg Book: Flat Earth: The History of an Infamous Idea Book: Mere Thermodynamics Book: CGP revision guides Book: Hiding the Elephant: How Magicians Invented the Impossible Book: Back of the Envelope Physics Web Watch

    Science.gov (United States)

    2009-07-01

    WE RECOMMEND Doctor Atomic The new Doctor Atomic opera provkes discussion on ethics I Cyborg The world's first human cyborg shares his life story in I Cyborg Flat Earth: The History of an Infamous Idea Flat Earth gives us a different perspective on creationism Mere Thermodynamics An introductory text on the three laws CGP revision guides This revision guide suits all courses and every pocket Hiding the Elephant: How Magicians Invented the Impossible The mystery of many illusions are solved in this book Back of the Envelope Physics This reference deserves a place on your bookshelf WORTH A LOOK Doctor Atomic The DVD doesn't do justice to the live performance Digital stopclock with external trigger Use these stopclocks when you need an external trigger WEB WATCH Webcasts reach out to an online audience

  2. Health effects models for nuclear power plant accident consequence analysis. Part 1, Introduction, integration, and summary: Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.S. [Harvard School of Public Health, Boston, MA (United States); Abrahmson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Inhalation Toxicology Research Inst., Albuquerque, NM (United States); Gilbert, E.S. [Battelle Pacific Northwest Lab., Richland, WA (United States)

    1993-10-01

    This report is a revision of NUREG/CR-4214, Rev. 1, Part 1 (1990), Health Effects Models for Nuclear Power Plant Accident Consequence Analysis. This revision has been made to incorporate changes to the Health Effects Models recommended in two addenda to the NUREG/CR-4214, Rev. 1, Part 11, 1989 report. The first of these addenda provided recommended changes to the health effects models for low-LET radiations based on recent reports from UNSCEAR, ICRP and NAS/NRC (BEIR V). The second addendum presented changes needed to incorporate alpha-emitting radionuclides into the accident exposure source term. As in the earlier version of this report, models are provided for early and continuing effects, cancers and thyroid nodules, and genetic effects. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes are considered. Linear and linear-quadratic models are recommended for estimating the risks of seven types of cancer in adults - leukemia, bone, lung, breast, gastrointestinal, thyroid, and ``other``. For most cancers, both incidence and mortality are addressed. Five classes of genetic diseases -- dominant, x-linked, aneuploidy, unbalanced translocations, and multifactorial diseases are also considered. Data are provided that should enable analysts to consider the timing and severity of each type of health risk.

  3. Equipment Operational Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Greenwalt, B; Henderer, B; Hibbard, W; Mercer, M

    2009-06-11

    The Iraq Department of Border Enforcement is rich in personnel, but poor in equipment. An effective border control system must include detection, discrimination, decision, tracking and interdiction, capture, identification, and disposition. An equipment solution that addresses only a part of this will not succeed, likewise equipment by itself is not the answer without considering the personnel and how they would employ the equipment. The solution should take advantage of the existing in-place system and address all of the critical functions. The solutions are envisioned as being implemented in a phased manner, where Solution 1 is followed by Solution 2 and eventually by Solution 3. This allows adequate time for training and gaining operational experience for successively more complex equipment. Detailed descriptions of the components follow the solution descriptions. Solution 1 - This solution is based on changes to CONOPs, and does not have a technology component. It consists of observers at the forts and annexes, forward patrols along the swamp edge, in depth patrols approximately 10 kilometers inland from the swamp, and checkpoints on major roads. Solution 2 - This solution adds a ground sensor array to the Solution 1 system. Solution 3 - This solution is based around installing a radar/video camera system on each fort. It employs the CONOPS from Solution 1, but uses minimal ground sensors deployed only in areas with poor radar/video camera coverage (such as canals and streams shielded by vegetation), or by roads covered by radar but outside the range of the radar associated cameras. This document provides broad operational requirements for major equipment components along with sufficient operational details to allow the technical community to identify potential hardware candidates. Continuing analysis will develop quantities required and more detailed tactics, techniques, and procedures.

  4. Charging equipment. Ladegeraet

    Energy Technology Data Exchange (ETDEWEB)

    Neumann, E

    1981-09-17

    The invention refers to a charging equipment, particularly on board charging equipment for charging traction batteries of an electric vehicle from the AC mains supply, consisting of a DC converter, which contains a controlled power transistor, a switching off unloading circuit and a power transmitter, where the secondary winding is connected in series with a rectifier diode, and a smoothing capacitor is connected in parallel with this series circuit. A converter module is provided, which consists of two DC voltage converters, whose power transistors are controlled by a control circuit in opposition with a phase displacement of 180/sup 0/.

  5. Waste Isolation Pilot Plant No-Migration Variance Petition. Revision 1, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, Arlen

    1990-03-01

    The purpose of the WIPP No-Migration Variance Petition is to demonstrate, according to the requirements of RCRA {section}3004(d) and 40 CFR {section}268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the facility for as long as the wastes remain hazardous. The DOE submitted the petition to the EPA in March 1989. Upon completion of its initial review, the EPA provided to DOE a Notice of Deficiencies (NOD). DOE responded to the EPA`s NOD and met with the EPA`s reviewers of the petition several times during 1989. In August 1989, EPA requested that DOE submit significant additional information addressing a variety of topics including: waste characterization, ground water hydrology, geology and dissolution features, monitoring programs, the gas generation test program, and other aspects of the project. This additional information was provided to EPA in January 1990 when DOE submitted Revision 1 of the Addendum to the petition. For clarity and ease of review, this document includes all of these submittals, and the information has been updated where appropriate. This document is divided into the following sections: Introduction, 1.0: Facility Description, 2.0: Waste Description, 3.0; Site Characterization, 4.0; Environmental Impact Analysis, 5.0; Prediction and Assessment of Infrequent Events, 6.0; and References, 7.0.

  6. Experimental equipment, ch. 6

    International Nuclear Information System (INIS)

    Boomstra, F.; Hoogenboom, A.M.; Prins, C.M.; Strasters, B.A.; Vermeer, A.; Wit, P. de; Zwol, N.A. van.

    1977-01-01

    The experimental equipment in use at Utrecht university is discussed. Attention is paid to the tandem Van de Graaff accelerator and the 4MV and 1MV accelerators. The detection systems for gamma-ray spectroscopy are reviewed with emphasis on the compton-suppression spectrometer. The data-handling system used for experiments with the tandem is also briefly discussed

  7. Equipment gift to Monaco

    International Nuclear Information System (INIS)

    1970-01-01

    Research work at the Agency's Laboratory of Marine Radioactivity in Monaco, including that concerned with pollution of the sea, has been made more effective by its latest acquisition of equipment. This is a spectrophotometer donated by the Federal Republic of Germany. (author)

  8. Lifetime of Mechanical Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Leland, K.

    1999-07-01

    The gas plant at Kaarstoe was built as part of the Statpipe gas transport system and went on stream in 1985. In 1993 another line was routed from the Sleipner field to carry condensate, and the plant was extended accordingly. Today heavy additional supply- and export lines are under construction, and the plant is extended more than ever. The main role of the factory is to separate the raw gas into commercial products and to pump or ship it to the markets. The site covers a large number of well-known mechanical equipment. This presentation deals with piping, mechanical and structural disciplines. The lifetime of mechanical equipment is often difficult to predict as it depends on many factors, and the subject is complex. Mechanical equipment has been kept in-house, which provides detailed knowledge of the stages from a new to a 14 years old plant. The production regularity has always been very high, as required. The standard of the equipment is well kept, support systems are efficient, and human improvisation is extremely valuable.

  9. Safeguards techniques and equipment

    International Nuclear Information System (INIS)

    1997-01-01

    The current booklet is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. As new verification measures continue to be developed, the material in the booklet will be periodically reviewed and updated versions issued. (author)

  10. Equipping tomorrow's fire manager

    Science.gov (United States)

    Christopher A. Dicus

    2008-01-01

    Fire managers are challenged with an ever-increasing array of both responsibilities and critics. As in the past, fire managers must master the elements of fire behavior and ecology using the latest technologies. In addition, today’s managers must be equipped with the skills necessary to understand and liaise with a burgeoning group of vocal stakeholders while also...

  11. Electrical equipment design library

    International Nuclear Information System (INIS)

    1994-01-01

    This book guides the design supervision, construction order for electrical equipment. The contents of this library are let's use electricity like this, leading-in-pole and casual power, electric pole install below 300KVA, electric pole install below 301∼1000KVA, electric pole install exceed 1000KVA, rooftop install exceed 1000KVA, CUBICLE type, 154KV services. It adds an appendix.

  12. Orphee reactor experimental equipment

    International Nuclear Information System (INIS)

    1987-01-01

    Experimental equipment around the ORPHEE reactor is presented. The neutron source; and the spectrometers and sample environment (inelastic and quasi-elastic scattering, elastic scattering, spread scattering, small angle scattering) are described. An experiment proposal and reports guide is supplied [fr

  13. Seismic qualification of equipment

    International Nuclear Information System (INIS)

    Heidebrecht, A.C.; Tso, W.K.

    1983-03-01

    This report describes the results of an investigation into the seismic qualification of equipment located in CANDU nuclear power plants. It is particularly concerned with the evaluation of current seismic qualification requirements, the development of a suitable methodology for the seismic qualification of safety systems, and the evaluation of seismic qualification analysis and testing procedures

  14. Underground coal equipment

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, J.

    2002-12-01

    This paper reports on increasing automation and enhanced productivity on longwalls, new development cutting and bolting technologies and haulage systems. Amongst equipment discussed is DBT's Electra series EL3000 shearer, the Dosco LH1400 roadheader with onboard bolters, and Joy 12 CM30 continuous miners. 4 photos.

  15. Visual communication and terminal equipment

    International Nuclear Information System (INIS)

    Kang, Cheol Hui

    1988-06-01

    This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

  16. Visual communication and terminal equipment

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Cheol Hui

    1988-06-15

    This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

  17. Test plan: Air intake shaft performance test -- Addendum for obtaining cores in the Culebra for radionuclide retardation studies

    International Nuclear Information System (INIS)

    Gelbard, F.

    1991-10-01

    Core samples are needed for obtaining data on radionuclide retardation. The cores will be used to first determine local basic properties of Culebra rock such as permeability, structural integrity, fracture spacing, and fracture size. These quantities will then be used to design a laboratory experimental program to determine radionuclide retardation in a column flow apparatus using the cores obtained in this project. This addendum covers only the coring activities necessary to retrieve Culebra cores. The laboratory work will be documented in a separate test plan. It is anticipated that Culebra rock samples will be highly fractured, with a fracture spacing on the order of 2 to 3 inches To obtain representative core samples that are intact, horizontal cores about 6 inches in diameter and several feet long will be needed. These cores will provide a good indication of Culebra rock fracturing and provide several samples needed to conduct column flow experiments. If the rock is so fractured that only rubble is obtained, then the rubble will be used in the column experiments. In addition, as a byproduct of the coring operation, natural groundwater collected from the holes will be used to develop a synthetic brine for the laboratory experiments

  18. An eight pushbutton control system for the PSU ultra-safe nuclear plant: Addendum to annual report

    International Nuclear Information System (INIS)

    Schultz, M.A.

    1988-10-01

    The control system described in this report was developed for a ''Light Water Ultra-Safe Plant Concept'' studied at Penn State during a 2 year program funded by the Department of Energy. A reconfigured pressurized water reactor was designed which eliminated the conventional PWR pressurizer and added an active pumping system with a large dedicated water storage tank to control pressure. The thermal hydraulics aspects of the design were studied and reported in several master's theses and other addendum reports and first annual report. In addition to improving the inherent safety of an advanced plant by changes in the thermal hydraulic aspects of the design, a new approach to control system organization and design should also be included in an advanced plant. The study presented in this report modifies a conventional PWR plant control system to the needs of the Ultra-Safe Plant Concept and then describes implementation of the control system in a distributed network of control computers. The end result is a control system that is much simpler at the operator level. This simplicity should eliminate the possibility of operator error in the Ultra-Safe plant

  19. Assessment of the radiological impact of the Windscale reactor fire, October 1957. Addendum to report NRPB R135

    Energy Technology Data Exchange (ETDEWEB)

    Crick, M J; Linsley, G S

    1983-01-01

    The assessment described has involved a review of previously unpublished data, in order to establish the quantities of nuclides released from materials undergoing irradiation in the pile at the time of the fire. Of these additional nuclides, only polonium-210 has been shown to make a significant contribution to the estimate of the collective effective dose equivalent to the population from the Windscale fire. The previous estimate of 1.2 x 10/sup 3/ man Sv for the collective effective dose equivalent commitment to the population of the UK and Northern Europe has been increased by 67% to 2.0 x 10/sup 3/ man Sv. This change is within the range of uncertainty of the original estimate. The influence of the addition on the theoretical estimate of the upper limit of possible health effects is discussed in this addendum and its foreword. With the inclusion of the additional nuclides, the inhalation pathway has become the overall largest contributor to this population dose, followed by the milk ingestion pathway; the largest nuclide contribution comes from iodine-131, followed by polonium-210. Some perspective may be provided on the contribution due to polonium-210 by noting that it is approximately one-tenth of that arising annually due to naturally occurring polonium-210, and less than one-hundredth of that due annually to the total natural background radiation.

  20. Performance evaluation of alternative fuel/engine concepts 1990- 1995. Final report including addendum of diesel vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Nylund, N.O.; Ikonen, M.; Kytoe, M.; Lappi, M.; Westerholm, M.; Laurikko, J. [VTT Energy, Espoo (Finland). Energy Use

    1996-12-31

    Annex V within the IEA Agreement on Alternative Motor Fuels is the first subtask to generate new experimental data. The objective of the task is to generate information on the emission potential of alternative fuels in severe operating conditions and to evaluate new emission measurement methods. The work was carried out in three phases, Engine Tests, Vehicle Tests and Addendum of Diesel Vehicles. The work was carried out at VTT (Technical Research Centre of Finland) as a cost shared operation. Participants were Belgium (Parts Two and Three), Canada (Parts One and Two), Finland, Italy (Part One), Japan, the Netherlands Sweden and USA. The United Kingdom also joined at the end of the Annex. The work included 143 different vehicle/fuel/temperature combinations. FTP type emission tests were run on 14 vehicles powered with different gasoline compositions, methanol (M50 and M85), ethanol (E85), LPG, CNG and diesel. Both regulated and unregulated emission components were measured using the most up-to-date emissions measurement technology. The results indicated, that today`s advanced gasoline vehicles must be considered rather clean. Diesel is comparable with gasoline in the case of CO and HC. M85 gives low emissions in warm conditions, but unburned methanol must be controlled. Natural gas and LPG are inherently clean fuels which, using up-to-date engine technology, give low emissions in all conditions. (orig.) (29 refs.)

  1. Psychometric properties of the Brazilian version of the Pittsburgh Sleep Quality Index Addendum for PTSD (PSQI-A

    Directory of Open Access Journals (Sweden)

    Jair B. Barbosa Neto

    2014-12-01

    Full Text Available Objective: Sleep disturbances play a fundamental role in the pathophysiology posttraumatic stress disorder (PTSD, and are not only a secondary feature. The aim of this study was to validate and assess the psychometric properties of the Brazilian version of the Pittsburgh Sleep Quality Index Addendum for PTSD (PSQI-A-BR, a self-report instrument designed to assess the frequency of seven disruptive nocturnal behaviors, in a sample of participants with and without PTSD. Methods: PSQI-A was translated into Brazilian Portuguese and applied to a convenience sample of 190 volunteers, with and without PTSD, who had sought treatment for the consequences of a traumatic event. Results: The PSQI-A-BR displayed satisfactory internal consistency (Cronbach's coefficient of 0.83 between all items and convergent validity with the Clinician Administered PTSD Scale (CAPS, even when excluding sleep-related items (r = 0.52. Test-retest yielded high agreement in the global PSQI-A-BR, with good stability over time (r = 0.88. A global PSQI-A-BR cutoff score of 7 yielded a sensitivity of 79%, specificity of 64%, and a global score of 7 yielded a positive predictive value of 93% for discriminating participants with PTSD from those without PTSD. Conclusion: The PSQI-A-BR is a valid instrument for PTSD assessment, applicable to both clinical and research settings.

  2. Equipment cost optimization

    International Nuclear Information System (INIS)

    Ribeiro, E.M.; Farias, M.A.; Dreyer, S.R.B.

    1995-01-01

    Considering the importance of the cost of material and equipment in the overall cost profile of an oil company, which in the case of Petrobras, represents approximately 23% of the total operational cost or 10% of the sales, an organization for the optimization of such costs has been established within Petrobras. Programs are developed aiming at: optimization of life-cycle cost of material and equipment; optimization of industrial processes costs through material development. This paper describes the methodology used in the management of the development programs and presents some examples of concluded and ongoing programs, which are conducted in permanent cooperation with suppliers, technical laboratories and research institutions and have been showing relevant results

  3. X-ray equipment

    International Nuclear Information System (INIS)

    Redmayne, I.G.B.

    1988-01-01

    The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.)

  4. X-ray equipment

    Energy Technology Data Exchange (ETDEWEB)

    Redmayne, I.G.B.

    1988-01-06

    The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.).

  5. Tube for irradiation equipment

    International Nuclear Information System (INIS)

    Goehrich, K.; Vogt, H.

    1979-01-01

    This patent describes a tube for irradiation equipment for limiting an emergent beam, with a baseplate, possessing a central aperture, intended for attaching to the equipment, as well as four carrier plates, each of which possesses a limiting edge and a sliding edge located at right angles thereto. The carrier plates are located parallel to the baseplate, the limiting edge of each carrier plate resting against the sliding edge of the adjacent carrier plate and each of the two mutually opposite pairs of carrier plates being displaceable, parallel to the direction of its sliding edges and symmetrically to the center of the transmission aperture, for the purpose of continuously varying the transmission aperture defined by the limiting edges, during which displacement each of the displaced carrier plates carries with it the carrier plate, resting against the limiting edge of the former plate, parallel to the direction of the limiting edge of the latter plate. 8 claims

  6. Equipment for isotope diagnostics

    International Nuclear Information System (INIS)

    Platz, W.

    1976-01-01

    The invention concerns an improvement of equipment for isotope diagnostics allowing to mark special intensity ranges of the recorded measurements by means of different colors. For undisturbed operation it is of advantage to avoid electric circuits between movable and unmovable parts of the color recorder. According to the invention, long gear wheels of glass fiber-reinforced polyamide are used for these connections. (ORU) [de

  7. Soviet equipment flies in

    CERN Multimedia

    CERN PhotoLab

    1978-01-01

    End of February 1977 a Soviet Ilyushin-76 heavy freight aircraft landed at Cointrin airport having on board fifty large wire proprtional chambers and associated apparatus, together weighing 10 tons, supplied by the Joint Institute for Nuclear Research, Dubna, USSR. The equipment was for the CERN- Dubna-Munich-Saclay experiment NA4 on deep inelastic muon scattering being set up in the North Area of SPS. See Weekly Bulletin 11/78.

  8. Labelling of equipment dispensers.

    Science.gov (United States)

    Gray, D C

    1993-01-01

    A new labelling system for use on medical equipment dispensers is tested. This system uses one of the objects stored in each unit of the dispenser as the 'label', by attaching it to the front of the dispenser with tape. The new system was compared to conventional written labelling by timing subjects asked to select items from two dispensers. The new system was 27% quicker than the conventional system. Images Fig. 1 PMID:8110335

  9. Equipment Obsolescence Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Redmond, J.

    2014-07-01

    Nuclear Power Plant (NPP) Operators are challenged with securing reliable supply channels for safety related equipment due to equipment obsolescence. Many Original Equipment Manufacturers (OEMs) have terminated production of spare parts and product life-cycle support. The average component life cycles are much shorter than the NPP design life, which means that replacement components and parts for the original NPP systems are not available for the complete design life of the NPPs. The lack or scarcity of replacement parts adversely affects plant reliability and ultimately the profitability of the affected NPPs. This problem is further compounded when NPPs pursue license renewal and approval for plant-life extension. A reliable and predictable supply of replacement co components is necessary for NPPs to remain economically competitive and meet regulatory requirements and guidelines. Electrical and I and C components, in particular, have short product life cycles and obsolescence issues must be managed pro actively and not reactively in order to mitigate the risk to the NPP to ensure reliable and economic NPP operation. (Author)

  10. Personal protective equipment

    International Nuclear Information System (INIS)

    2004-01-01

    This Practical Radiation Technical Manual is one of a series that has been designed to provide guidance on radiological protection for employers, radiation protection officers, managers and other technically competent persons who have responsibility for ensuring the safety of employees working with ionizing radiation. The Manual may be used with the appropriate IAEA Practical Radiation Safety Manuals to provide training, instruction and information for all employees engaged in work with ionizing radiation. Personal protective equipment (PPE) includes clothing or other special equipment that is issued to individual workers to provide protection against actual or potential exposure to ionizing radiations. It is used to protect each worker against the prevailing risk of external or internal exposure in circumstances in which it is not reasonably practicable to provide complete protection by means of engineering controls or administrative methods. Adequate personal protection depends on PPE being correctly selected, fitted and maintained. Appropriate training for the users and arrangements to monitor usage are also necessary to ensure that PPE provides the intended degree of protection effectively. This Manual explains the principal types of PPE, including protective clothing and respiratory protective equipment (RPE). Examples of working procedures are also described to indicate how PPE should be used within a safe system of work. The Manual will be of most benefit if it forms part of a more comprehensive training programme or is supplemented by the advice of a qualified expert in radiation protection. Some of the RPE described in this Manual should be used under the guidance of a qualified expert

  11. Addendum to ‘Understanding risks in the light of uncertainty: low-probability, high-impact coastal events in cities’

    Science.gov (United States)

    Galarraga, Ibon; Sainz de Murieta, Elisa; Markandya, Anil; María Abadie, Luis

    2018-02-01

    This addendum adds to the analysis presented in ‘Understanding risks in the light of uncertainty: low-probability, high-impact coastal events in cities’ Abadie et al (2017 Environ. Res. Lett. 12 014017). We propose to use the framework developed earlier to enhance communication and understanding of risks, with the aim of bridging the gap between highly technical risk management discussion to the public risk aversion debate. We also propose that the framework could be used for stress-testing resilience.

  12. GAMBIT. The global and modular beyond-the-standard-model inference tool. Addendum for GAMBIT 1.1. Mathematica backends, SUSYHD interface and updated likelihoods

    Energy Technology Data Exchange (ETDEWEB)

    Athron, Peter; Balazs, Csaba [Monash University, School of Physics and Astronomy, Melbourne, VIC (Australia); Australian Research Council Centre of Excellence for Particle Physics at the Tera-scale (Australia); Bringmann, Torsten; Dal, Lars A.; Gonzalo, Tomas E.; Krislock, Abram; Raklev, Are [University of Oslo, Department of Physics, Oslo (Norway); Buckley, Andy [University of Glasgow, SUPA, School of Physics and Astronomy, Glasgow (United Kingdom); Chrzaszcz, Marcin [Universitaet Zuerich, Physik-Institut, Zurich (Switzerland); Polish Academy of Sciences, H. Niewodniczanski Institute of Nuclear Physics, Krakow (Poland); Conrad, Jan; Edsjoe, Joakim; Farmer, Ben; Lundberg, Johan [AlbaNova University Centre, Oskar Klein Centre for Cosmoparticle Physics, Stockholm (Sweden); Stockholm University, Department of Physics, Stockholm (Sweden); Cornell, Jonathan M. [McGill University, Department of Physics, Montreal, QC (Canada); Dickinson, Hugh [University of Minnesota, Minnesota Institute for Astrophysics, Minneapolis, MN (United States); Jackson, Paul; White, Martin [Australian Research Council Centre of Excellence for Particle Physics at the Tera-scale (Australia); University of Adelaide, Department of Physics, Adelaide, SA (Australia); Kvellestad, Anders; Savage, Christopher [NORDITA, Stockholm (Sweden); McKay, James [Imperial College London, Department of Physics, Blackett Laboratory, London (United Kingdom); Mahmoudi, Farvah [Lyon 1 Univ., ENS de Lyon, CNRS, Centre de Recherche Astrophysique de Lyon UMR5574, Saint-Genis-Laval (France); CERN, Theoretical Physics Department, Geneva (Switzerland); Institut Universitaire de France, Paris (France); Martinez, Gregory D. [University of California, Physics and Astronomy Department, Los Angeles, CA (United States); Putze, Antje [LAPTh, Universite de Savoie, CNRS, Annecy-le-Vieux (France); Ripken, Joachim [Max Planck Institute for Solar System Research, Goettingen (Germany); Rogan, Christopher [Harvard University, Department of Physics, Cambridge, MA (United States); Saavedra, Aldo [Australian Research Council Centre of Excellence for Particle Physics at the Tera-scale (Australia); University of Sydney, Centre for Translational Data Science, Faculty of Engineering and Information Technologies, School of Physics, Sydney, NSW (Australia); Scott, Pat [Imperial College London, Department of Physics, Blackett Laboratory, London (United Kingdom); Seo, Seon-Hee [Seoul National University, Department of Physics and Astronomy, Seoul (Korea, Republic of); Serra, Nicola [Universitaet Zuerich, Physik-Institut, Zurich (Switzerland); Weniger, Christoph [University of Amsterdam, GRAPPA, Institute of Physics, Amsterdam (Netherlands); Wild, Sebastian [DESY, Hamburg (Germany); Collaboration: The GAMBIT Collaboration

    2018-02-15

    In Ref. (GAMBIT Collaboration: Athron et. al., Eur. Phys. J. C.arXiv:1705.07908, 2017) we introduced the global-fitting framework GAMBIT. In this addendum, we describe a new minor version increment of this package. GAMBIT 1.1 includes full support for Mathematica backends, which we describe in some detail here. As an example, we backend SUSYHD (Vega and Villadoro, JHEP 07:159, 2015), which calculates the mass of the Higgs boson in the MSSM from effective field theory. We also describe updated likelihoods in PrecisionBit and DarkBit, and updated decay data included in DecayBit. (orig.)

  13. GAMBIT: the global and modular beyond-the-standard-model inference tool. Addendum for GAMBIT 1.1: Mathematica backends, SUSYHD interface and updated likelihoods

    Science.gov (United States)

    Athron, Peter; Balazs, Csaba; Bringmann, Torsten; Buckley, Andy; Chrząszcz, Marcin; Conrad, Jan; Cornell, Jonathan M.; Dal, Lars A.; Dickinson, Hugh; Edsjö, Joakim; Farmer, Ben; Gonzalo, Tomás E.; Jackson, Paul; Krislock, Abram; Kvellestad, Anders; Lundberg, Johan; McKay, James; Mahmoudi, Farvah; Martinez, Gregory D.; Putze, Antje; Raklev, Are; Ripken, Joachim; Rogan, Christopher; Saavedra, Aldo; Savage, Christopher; Scott, Pat; Seo, Seon-Hee; Serra, Nicola; Weniger, Christoph; White, Martin; Wild, Sebastian

    2018-02-01

    In Ref. (GAMBIT Collaboration: Athron et. al., Eur. Phys. J. C. arXiv:1705.07908, 2017) we introduced the global-fitting framework GAMBIT. In this addendum, we describe a new minor version increment of this package. GAMBIT 1.1 includes full support for Mathematica backends, which we describe in some detail here. As an example, we backend SUSYHD (Vega and Villadoro, JHEP 07:159, 2015), which calculates the mass of the Higgs boson in the MSSM from effective field theory. We also describe updated likelihoods in PrecisionBit and DarkBit, and updated decay data included in DecayBit.

  14. GAMBIT. The global and modular beyond-the-standard-model inference tool. Addendum for GAMBIT 1.1. Mathematica backends, SUSYHD interface and updated likelihoods

    International Nuclear Information System (INIS)

    Athron, Peter; Balazs, Csaba; Bringmann, Torsten; Dal, Lars A.; Gonzalo, Tomas E.; Krislock, Abram; Raklev, Are; Buckley, Andy; Chrzaszcz, Marcin; Conrad, Jan; Edsjoe, Joakim; Farmer, Ben; Lundberg, Johan; Cornell, Jonathan M.; Dickinson, Hugh; Jackson, Paul; White, Martin; Kvellestad, Anders; Savage, Christopher; McKay, James; Mahmoudi, Farvah; Martinez, Gregory D.; Putze, Antje; Ripken, Joachim; Rogan, Christopher; Saavedra, Aldo; Scott, Pat; Seo, Seon-Hee; Serra, Nicola; Weniger, Christoph; Wild, Sebastian

    2018-01-01

    In Ref. (GAMBIT Collaboration: Athron et. al., Eur. Phys. J. C.arXiv:1705.07908, 2017) we introduced the global-fitting framework GAMBIT. In this addendum, we describe a new minor version increment of this package. GAMBIT 1.1 includes full support for Mathematica backends, which we describe in some detail here. As an example, we backend SUSYHD (Vega and Villadoro, JHEP 07:159, 2015), which calculates the mass of the Higgs boson in the MSSM from effective field theory. We also describe updated likelihoods in PrecisionBit and DarkBit, and updated decay data included in DecayBit. (orig.)

  15. Polarized proton Target-III operators manual, revision A

    International Nuclear Information System (INIS)

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

    1976-04-01

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

  16. Basic Drafting. Revised.

    Science.gov (United States)

    Schertz, Karen

    This introductory module on drafting includes the technical content and tasks necessary for a student to be employed in an entry-level drafting occupation. The module contains 18 instructional units that cover the following topics: introduction to drafting; tools and equipment; supplies and materials; sketching; scales; drawing format; lettering;…

  17. Scientific Equipment Division - Overview

    International Nuclear Information System (INIS)

    Halik, J.

    2001-01-01

    Full text: The Scientific Equipment Division consists of the Design Group and the Mechanical Workshop. The activity of the Division includes the following: - designing of devices and equipment for experiments in physics, their mechanical construction and assembly. In particular, there are vacuum chambers and installations for HV and UHV; - maintenance and upgrading of the existing installations and equipment in our Institute; - participation of our engineers and technicians in design works, equipment assembly and maintenance for experiments in foreign laboratories. The Design Group is equipped with PC-computers and AutoCAD graphic software (release 2000 and Mechanical Desktop 4.0) and a AO plotter, what allows us to make drawings and 2- and 3-dimensional mechanical documentation to the world standards. The Mechanical Workshop can offer a wide range of machining and treatment methods with satisfactory tolerances and surface quality. It offers the following possibilities: - turning - cylindrical elements of a length up to 2000 mm and a diameter up to 400 mm, and also disc-type elements of a diameter up to 600 mm and a length not exceeding 300 mm; - milling - elements of length up to 1000 mm and gear wheels of diameter up to 300 mm; - grinding - flat surfaces of dimensions up to 300 mm x 1000 mm and cylindrical elements of a diameter up to 200 mm and a length up to 800 mm; - drilling - holes of a diameter up to 50 mm; - welding - electrical and gas welding, including TIG vacuum-tight welding; - soft and hard soldering; - mechanical works including precision engineering; - plastics treatment - machining and polishing using diamond milling, modelling, lamination of various shapes and materials, including plexiglas, scintillators and light-guides; - painting - paint spraying with possibility of using furnace-fred drier of internal dimensions of 800 mm x 800 mm x 800 mm. Our workshop posses CNC milling machine which can be used for machining of work-pieces up to 500 kg

  18. Data package addendum for COBRA-1A2 life extension to 400 EFPD

    International Nuclear Information System (INIS)

    Hecht, S.L.; Ermi, A.M.

    1994-01-01

    The COBRA-1A experiment was originally designed for irradiations up to 350 effective full power days (EFPD) in EBR-II. Three of the seven B7A test capsules were discharged after 88.6 EFPD (COBRA-1A1; EBR-II designation X516), while the remaining four capsules continued to be irradiated to a goal exposure of 300 EFPD (COBRA-1A2; EBR-II designation X516A). However, it was recently decided that COBRA-1A2 was to remain in the reactor during Run 170, giving and nominal end-of-life (EOL) exposure of 375 EFPD. Since the revised test exposure exceeds the design basis given in supporting analyses, amended analyses are provided herein, giving the technical bases for the extended irradiation. This report describes the safety analysis for the extension of the COBRA-1A2 test (X516A) to 400 effective full power days in FBR-II

  19. Mining face equipment

    Energy Technology Data Exchange (ETDEWEB)

    G, Litvinskiy G; Babyuk, G V; Yakovenko, V A

    1981-01-07

    Mining face equipment includes drilling advance wells, drilling using explosives on the contour bore holes, loading and transporting the crushed mass, drilling reinforcement shafts, injecting reinforcement compounds and moving the timber. Camouflet explosives are used to form relaxed rock stress beyond the mining area to decrease costs of reinforcing the mining area by using nonstressed rock in the advance well as support. The strengthening solution is injected through advanced cementing wells before drilling the contour bores as well as through radial cementing wells beyond the timbers following loading and transport of the mining debris. The advance well is 50-80 m.

  20. Coal ash monitoring equipment

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, C G; Wormald, M R

    1978-10-02

    The monitoring equipment is used to determine the remainder from combustion (ash slack) of coal in wagons designed for power stations. Next to the rails, a neutron source (252 Cf, 241 Am/Be) is situated, which irradiates the coal with neutrons at a known dose, which produces the reaction 27 Al (n ..gamma..) Al 28. The aluminium content is a measure of the remainder. The 1.78 MeV energy is measured downstream of the rail with a detector. The neutron source can only act in the working position of a loaded wagon.

  1. Management of Transportation Equipment.

    Science.gov (United States)

    1982-11-01

    Record% % %. "jP -M -. M LIh TRANSPORTATION MAENTKENAI4CE SHOP WORKLOAD CONTROL WORK CENTER SADR A-OR .a’* tLR 4.,R53 8114LM 0 o 251 50 75 100 125 ISO ...PDBP 06 7 4892 TRACTOR, WHEEL, INDUST, 14001-20000 PDBP 06 7 4893 TRACTOR, WHEEL, INDUST, 20001-27000 PDBP 06 7 4894 TRACTOR, WHEEL, INDUST, 27001 PDBP...27K TRACTOR, WHEEL, INDUST, 27001 PDBP & UP P-i LINE ITEM 07 LIGHTING AND POWER GENERATION EQUIPMENT 5110 T FLOODLIGHT ELEC FLOODLIGHT, ELEC, TRUCK

  2. Californium-252 Program Equipment Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Chattin, Fred Rhea [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wilson, Kenton [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ezold, Julie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-12-01

    To successfully continue the 252Cf production and meet the needs of the customers, a comprehensive evaluation of the Building 7920 processing equipment was requested to identify equipment critical to the operational continuity of the program.

  3. Drilling Addendum to Resource Assessment of Low- and Moderate-Temperature Geothermal Waters in Calistoga, Napa County, California

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, Gary C.; Bacon, C. Forrest; Chapman, Rodger H.; Chase, Gordon W.; Majmundar, Hasmukhrai H.

    1981-05-01

    This addendum report presents the results of the California Division of Mines and Geology (CDMG) drilling program at Calistoga, California, which was the final geothermal-resource assessment investigation performed under terms of the second year contract (1979-80) between the U.S. Department of Energy (DOE) and the CDMG under the State Coupled Program. This report is intended to supplement information presented in CDMG's technical report for the project year, ''Resource Assessment of Low- and Moderate-Temperature Geothermal Waters in Calistoga, Napa County, California''. During the investigative phase of the CDMG's Geothermal Project, over 200 well-driller's reports were obtained from the Department of Water Resources (DWR). It was hoped that the interpretation and correlation of these logs would reveal the subsurface geology of the Upper Napa Valley and also provide a check for the various geophysical surveys that were performed in the course of the study. However, these DWR driller logs proved to be inadequate due to the brief, non-technical, and erroneous descriptions contained on the logs. As a result of the lack of useable drill-hole data, and because information was desired from,deeper horizons, it became evident that drilling some exploratory holes would be necessary in order to obtain physical evidence of the stratigraphy and aquifers in the immediate Calistoga area. Pursuant to this objective, a total of twelve sites were selected--four under jurisdiction of Napa County and eight under jurisdiction of the City of Calistoga. A moratorium is currently in existence within Napa County on most geothermal drilling, and environmental and time constraints precluded CDMG from obtaining the necessary site permits within the county. However, a variance was applied for and obtained from the City of Calistoga to allow CDMG to drill within the city limits. With this areal constraint and also funding limits in mind, six drilling sites

  4. Revised Rules for Concrete Bridges

    DEFF Research Database (Denmark)

    Thoft-Christensen, Palle; Jensen, F. M.; Middleton, C.

    This paper is based on research performed for the Highway Agency, London, UK under the project DPU/9/44 "Revision of Bridge Assessment Rules Based on Whole Life Performance: Concrete Bridges" It contains details of a methodology which can be used to generate Whole Life (WL) reliability profiles....... These WL reliability profiles may be used to establish revised rules for Concrete Bridges....

  5. Emotion Processes in Knowledge Revision

    Science.gov (United States)

    Trevors, Gregory J.; Kendeou, Panayiota; Butterfuss, Reese

    2017-01-01

    In recent years, a number of insights have been gained into the cognitive processes that explain how individuals overcome misconceptions and revise their previously acquired incorrect knowledge. The current study complements this line of research by investigating the moment-by-moment emotion processes that occur during knowledge revision using a…

  6. Philippines revises power plans

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, D.

    1988-02-01

    Following an unexpected surge in electricity demand the Philippines has revised its medium term power development programme. The sharp increase in electricity consumption follows three years of slack demand due to civil disturbances before the end of the Macros administration and the election of Corazon Aquino as President in 1986. Originally, the Aquino government's medium term power development plans called for about 500MW of generating capacity to be installed between 1986 and 1992. The three proposed plants were scheduled for commissioning in 1991 and 1992. However, a spurt in power demand growth during the past nine months has caused concern among industrialists that power shortages could occur by the end of the decade. So additional capacity will be installed to prevent an anticipated shortfall in electricity supplies by the early 1990s.

  7. Revised SRAC code system

    International Nuclear Information System (INIS)

    Tsuchihashi, Keichiro; Ishiguro, Yukio; Kaneko, Kunio; Ido, Masaru.

    1986-09-01

    Since the publication of JAERI-1285 in 1983 for the preliminary version of the SRAC code system, a number of additions and modifications to the functions have been made to establish an overall neutronics code system. Major points are (1) addition of JENDL-2 version of data library, (2) a direct treatment of doubly heterogeneous effect on resonance absorption, (3) a generalized Dancoff factor, (4) a cell calculation based on the fixed boundary source problem, (5) the corresponding edit required for experimental analysis and reactor design, (6) a perturbation theory calculation for reactivity change, (7) an auxiliary code for core burnup and fuel management, etc. This report is a revision of the users manual which consists of the general description, input data requirements and their explanation, detailed information on usage, mathematics, contents of libraries and sample I/O. (author)

  8. Microcomputers and the Improvement of Revision Skills.

    Science.gov (United States)

    Balajthy, Ernest; And Others

    1987-01-01

    Discusses use of word processing software as an effective tool in writing and revision instruction, and describes the role of the teacher. Examples of exercises that encourage revision and of software designed to teach effective revision skills are reviewed. (MBR)

  9. Coal mining equipment

    International Nuclear Information System (INIS)

    Stein, R.R.; Martin, T.W.

    1991-01-01

    The word in longwall components is big, and these larger components have price tags to match. The logic behind the greater investment is that it will yield high production rates and good uptime statistics. This is true in most cases. More important than single-shift tonnage records, average shift production continues to climb upwards. This paper reports on the quality, and more significantly, the quantity of service supplied for long-wall equipment, which has reached levels that would have been seen as unachievable when longwall mining was first introduced in the U.S. The school of thought then was that longwall would increase productivity in part by reducing the number of production units and thus reducing the number of personnel employed underground. The expectation of fewer employees turned out to be unrealistic. That was probably one reason that some early attempts to install longwall system looked more like failures than vision of the future

  10. Reactor fuel charging equipment

    International Nuclear Information System (INIS)

    Wade, Elman.

    1977-01-01

    In many types of reactor fuel charging equipment, tongs or a grab, attached to a trolley, housed in a guide duct, can be used for withdrawing from the core a selected spent fuel assembly or to place a new fuel assembly in the core. In these facilities, the trolley may have wheels that roll on rails in the guide duct. This ensures the correct alignment of the grab, the trolley and fuel assembly when this fuel assembly is being moved. By raising or lowering such a fuel assembly, the trolley can be immerged in the coolant bath of the reactor, whereas at other times it can be at a certain level above the upper surface of the coolant bath. The main object of the invention is to create a fuel handling apparatus for a sodium cooled reactor with bearings lubricated by the sodium coolant and in which the contamination of these bearings is prevented [fr

  11. Chapter 12. Space Heating Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Rafferty, Kevin D.

    1998-01-01

    The performance evaluation of space heating equipment for a geothermal application is generally considered from either of two perspectives: (a) selecting equipment for installation in new construction, or (b) evaluating the performance and retrofit requirements of an existing system. With regard to new construction, the procedure is relatively straightforward. Once the heating requirements are determined, the process need only involve the selection of appropriately sized hot water heating equipment based on the available water temperature. It is important to remember that space heating equipment for geothermal applications is the same equipment used in non-geothermal applications. What makes geothermal applications unique is that the equipment is generally applied at temperatures and flow rates that depart significantly from traditional heating system design. This chapter presents general considerations for the performance of heating equipment at non-standard temperature and flow conditions, retrofit of existing systems, and aspects of domestic hot water heating.

  12. Addendum to a proposal for ATLAS: a precision heavy-ion accelerator at Argonne National Laboratory

    International Nuclear Information System (INIS)

    1978-12-01

    This revised proposal for the construction of the Argonne Tandem-Linac Accelerator System (ATLAS) is in all essentials the same as the proposal originally presented to NUSAC in March 1978. The only differences worth mentioning are the plan to expand the experimental area somewhat more than was originally proposed and an increased cost, brought about principally by inflation. The outline presented is the same as in the original document, reproduced for the convenience of the reader. The objective of the proposed Argonne Tandem-Linac Accelerator System (ATLAS) is to provide precision beams of heavy ions for nuclear physics research in the region of projectile energies comparable to nuclear binding energies (5 to 25 MeV/A). By using the demonstrated potential of superconducting rf technology, beams of exceptional quality and flexibility can be obtained. The proposed system is designed to provide beams with tandem-like energy resolution and ease of energy variation, and the energy range is comparable to that of a approx. 50 MV tandem. In addition, the beam will be bunched into very short (approx. 50 psec) pulses, permitting fast-timing measurements that can open up major new experimental approaches

  13. A study on scar revision

    Directory of Open Access Journals (Sweden)

    Ashutosh Talwar

    2016-04-01

    Full Text Available Introduction: Scars are psychologically distressing for the patients and have an impact on the quality of life and self esteem of the patients. Scar revision is an aesthetic skill which is mastered by plastic surgeons and encroached now by dermatosurgeons. Scars on the face are aesthetically unacceptable and various techniques have been improvised for making a scar aesthetically acceptable. Various types of techniques are used for scar revision like W plasty, Z plasty and VY plasty. Aims: To see the efficacy of various scar revision techniques including Z plasty, VY plasty and W plasty in 30 patients with disfiguring scars. Methods: We selected twenty patients of disfiguring scars for the study. The scars from various causes including trauma and burns were included in our study. Various techniques of scar revision include Z plasty, W plasty and VY plasty were performed according to the type and site of scar. Results: Male: female was 1.5: 1. The scar revision surgery yielded excellent results with minimal complications including haematoma formation, secondary infection and delayed healing seen in 5% patients each. Regarding the efficacy of scar revision, excellent improvement was seen in 60% patients, moderate improvement was seen in 30% patients and mild improvement was seen in 10% patients. Conclusions: Dermatologists can employ a number of surgical scar revision techniques. While some are better suited to treat specific types of scars, they can be used in combination with each other or with adjunctive therapies to achieve optimal results.

  14. Equipment repair in coal mines

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, S

    1982-01-01

    Most equipment in Chinese coal mines consists of machinery and equipment produced in the 1950s; the efficiency of 4-62, CTD-57 and 70B/sub 2/ ventilators is 15% lower than that of new ones; that of SSM and AYaP pumps, 10% lower than of modern ones. Equipment renovation is done in three ways: replacing obsolete equipment with new equipment of the same type; improving the performance of existing equipment by introducing efficiency and reconstruction; and replacing obsolete equipment with advanced equipment. It is indicated that the second way, for example, replacement of 4-62 ventilator blades with a maximum efficiency of 73% by 4-72 ventilator blades raises its efficiency to 90%. Replacing the 8DA-8x3 water pump, having a maximum efficiency of 63%, with the 200D 43x3 pump with a maximum efficiency of 78%, enables an electricity savings of 7000 yuan per year, which exceeds all replacement costs (600 yuan). The need to improve equipment maintenance and preventive work to increase equipment service life and to introduce new techniques and efficiency is noted.

  15. Revised action plan of the Maintenance division for 1965, Annex 4

    International Nuclear Information System (INIS)

    Nikolic, M.

    1965-01-01

    The action plan presented in this annex is a revised version of the plan adopted in January 1965. It includes tasks of the mechanics, electrical and electronic equipment services. It includes a detailed list of planned and preventive maintenance actions related to the heavy water system, technical water system, helium system, reactor core, transportation equipment, hot cells, heating and ventilation systems in the reactor building, power supply system, auxiliary systems in the RA reactor building [sr

  16. 21 CFR 866.4540 - Immunonephelometer equipment.

    Science.gov (United States)

    2010-04-01

    ...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4540 Immunonephelometer equipment. (a) Identification. Immunonephelometer equipment for clinical use...

  17. 21 CFR 866.4520 - Immunofluorometer equipment.

    Science.gov (United States)

    2010-04-01

    ...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4520 Immunofluorometer equipment. (a) Identification. Immunofluorometer equipment for clinical use with...

  18. Equipment standards for interventional cardiology

    International Nuclear Information System (INIS)

    Dowling, A.; Gallagher, A.; Walsh, C.; Malone, J.

    2005-01-01

    Interventional radiology has seen rapid growth in cardiology and represents an alternative to hazardous surgery. Recently there has been a substantial growth in the number of procedures being performed and interventional cardiology (IC) procedures are the most common interventional procedures in Europe. Advances in imaging technology have facilitated the development of increasingly complex radiological IC equipment. Currently, the technology is developing at a rate ahead of supporting research, equipment standards and a regulatory framework. International standards play a key role in the design, manufacture and performance of radiological IC equipment. A survey of 12 IC systems (15 imaging chains) was conducted in Irish hospitals. The aim of the study was to assess the imbalance between rapidly advancing technology and existing standards and to propose recommendations for new IC equipment standards. The results demonstrate the need for definitive equipment requirements and standardisation in the design, manufacture, acceptance and maintenance of IC equipment. (authors)

  19. Generation of equipment response spectrum considering equipment-structure interaction

    International Nuclear Information System (INIS)

    Lee, Sang Hoon; Yoo, Kwang Hoon

    2005-01-01

    Floor response spectra for dynamic response of subsystem such as equipment, or piping in nuclear power plant are usually generated without considering dynamic interaction between main structure and subsystem. Since the dynamic structural response generally has the narrow-banded shapes, the resulting floor response spectra developed for various locations in the structure usually have high spectral peak amplitudes in the narrow frequency bands corresponding to the natural frequencies of the structural system. The application of such spectra for design of subsystems often leads to excessive design conservatisms, especially when the equipment frequency and structure are at resonance condition. Thus, in order to provide a rational and realistic design input for dynamic analysis and design of equipment, dynamic equipment-structure interaction (ESI) should be considered in developing equipment response spectrum which is particularly important for equipment at the resonance condition. Many analytical methods have been proposed in the past for developing equipment response spectra considering ESI. However, most of these methods have not been adapted to the practical applications because of either the complexities or the lack of rigorousness of the methods. At one hand, mass ratio among the equipment and structure was used as an important parameter to obtain equipment response spectra. Similarly, Tseng has also proposed the analytical method for developing equipment response spectra using mass ratio in the frequency domain. This method is analytically rigorous and can be easily validated. It is based on the dynamic substructuring method as applied to the dynamic soil-structure interaction (SSI) analysis, and can relatively easily be implemented for practical applications without to change the current dynamic analysis and design practice for subsystems. The equipment response spectra derived in this study are also based on Tseng's proposed method

  20. Revision of ASCE 4

    International Nuclear Information System (INIS)

    Nelson, T.A.; Murray, R.C.; Short, S.A.

    1995-01-01

    The original version of ASCE Standard 4, ''Seismic Analysis of Safety-Related Nuclear Structures'' was published in September 1986. It is ASCE policy to update its standards on a five year interval and the Working Group on Seismic Analysis of Safety Related Nuclear Structures was reconvened to formulate the revisions. The goal in updating the standard is to make sure that it is still relevant and that it incorporates the state of the practice in seismic engineering or, in some cases, where it has been demonstrated that state-of-the-art improvements need to be made to standard practice; new improvements are included. The contents of the new standard cover the same areas as the original version, with some additions. The contents are as follows: Input - response spectra and time histories; modeling of structures; analysis of structures; soil-structure interaction; input for subsystem analysis; special structures - buried pipes and conduits, earth-retaining walls, above-ground vertical tanks, raceways, and base-isolated structures; and an appendix providing seismic probabilistic risk assessment and margin assessment

  1. Contact activation: a revision.

    Science.gov (United States)

    Schmaier, A H

    1997-07-01

    In conclusion, a revised view of the contact system has been presented. This system has little to do with the initiation of hemostasis. Like lupus anticoagulants, deficiencies of contact proteins give prolonged APTTs but may be risk factors for thrombosis. BK from kininogens is a potent modulator of vascular biology inducing vasodilation, tissue plasminogen activator release, and prostacyclin liberation. Kininogens, themselves, are selective inhibitors of alpha-thrombin-induced platelet activation preventing alpha-thrombin from cleaving the cloned thrombin receptor after arginine41. Kininogens' alpha-thrombin inhibitory activity exists in intact kininogens, BK, and all of BK's breakdown products. HK also is the pivotal protein for contact protein assembly on endothelium. It is the receptor for prekallikrein which when bound to HK becomes activated to kallikrein by an endothelial cell enzyme system independent of activated forms of plasma factor XII. Prekallikrein activation on endothelial cells results in kinetically favorable single chain urokinase and plasminogen activation. Thus the "physiologic, negatively charged surface" for contact system activation is really the assembly of these proteins on cell membranes and activation by membrane-associated enzymes.

  2. Overall Equipment Effectiveness Implementation Criteria

    Science.gov (United States)

    Abramova, I. G.; Abramov, D. A.

    2018-01-01

    This article documents the methods applied in production control technics specifically focused on commonly used parameter OEE (Overall Equipment Effectiveness). The indicators of extensive and intensive use of equipment are considered. Their appointment this is comparison in the same type of production within the industry and comparison of single-type and / or different types of equipment in terms of capacity. However, it is shown that there is no possibility of revealing the reasons for the machine’s operation: productive / unproductive, with disturbances. Therefore, in the article reveals the approaches to calculating the indicator characterizing the direct operation of the equipment. The Machine Load coefficient is approaching closely to the indicator of the efficiency of the use of equipment. Methods analysis is proceeded through the historically applied techniques such as “Stopwatch” and “Motion” studies. Was performed the analysis of the efficiency index of OEE equipment using the comparable indexes performance of equipment in the Russian practice. An important indicator of OEE contains three components. The meaning of each of them reflects historically applicable indicators. The value of the availability of equipment indicator is close to the value of the equipment extensibility index. The value of the indicator of the efficiency of work can be compared with the characteristic of the capacity of the equipment and the indicator of the quality level can meet the requirements for compliance with the manufacturing technology. Shown that the sum of the values of the coefficient of “Availability” of the equipment and the value of the “Factor of compaction of working hours” are one. As well as the total value of the indicator “level of quality” and the coefficient of marriage given in the result unit. The measurability of the indicators makes it possible to make a prediction about efficiency of the equipment.

  3. 78 FR 73997 - Airworthiness Directives; Various Aircraft Equipped with Wing Lift Struts

    Science.gov (United States)

    2013-12-10

    ...-0023; Directorate Identifier 96-CE-072-AD; Amendment 39-17688; AD 99-01-05 R1] RIN 2120-AA64... Administration (FAA), DOT. ACTION: Final rule. SUMMARY: We are revising Airworthiness Directive (AD) 99-01-05 for certain aircraft equipped with wing lift struts. AD 99-01-05 required repetitively inspecting the wing...

  4. Information technology equipment cooling system

    Science.gov (United States)

    Schultz, Mark D.

    2014-06-10

    According to one embodiment, a system for removing heat from a rack of information technology equipment may include a sidecar indoor air to liquid heat exchanger that cools warm air generated by the rack of information technology equipment. The system may also include a liquid to liquid heat exchanger and an outdoor heat exchanger. The system may further include configurable pathways to connect and control fluid flow through the sidecar heat exchanger, the liquid to liquid heat exchanger, the rack of information technology equipment, and the outdoor heat exchanger based upon ambient temperature and/or ambient humidity to remove heat from the rack of information technology equipment.

  5. Management methodology for pressure equipment

    Science.gov (United States)

    Bletchly, P. J.

    Pressure equipment constitutes a significant investment in capital and a major proportion of potential high-risk plant in many operations and this is particularly so in an alumina refinery. In many jurisdictions pressure equipment is also subject to statutory regulation that imposes obligations on Owners of the equipment with respect to workplace safety. Most modern technical standards and industry codes of practice employ a risk-based approach to support better decision making with respect to pressure equipment. For a management system to be effective it must demonstrate that risk is being managed within acceptable limits.

  6. Cryogenic equipment; Materiel cryogenique

    Energy Technology Data Exchange (ETDEWEB)

    Leger, L; Javellaud, J; Caro, C; Gilguy, R; Testard, O

    1966-06-01

    The cryostats presented here were built from standard parts; this makes it possible to construct a great variety of apparatus at minimum cost. The liquid nitrogen and helium reservoirs were designed so as to reduce losses to a minimum, and so as to make the cryostats as autonomous as possible. The experimental enclosure which is generally placed in the lower part of the apparatus requires a separate study in every case. Furthermore, complete assemblies such as transfer rods, isolated traps and high vacuum valves, were designed with a similar regard for the economic aspects and for the need for standardization. This equipment thus satisfies a great variety of experimental needs; it is readily adaptable and the consumptions of helium and liquid nitrogen are very low. (authors) [French] De nombreuses experiences utilisant les basses temperatures, necessitent l'emploi d'un materiel cryogenique complexe n'existant pas dans le commerce. Les cryostats presentes ici ont ete realises a partir d'elements standard, ce qui permet, malgre la diversite des appareils, de realiser un ensemble a moindre frais. Les reservoirs d'azote et d'helium liquides ont ete concus de facon a limiter les pertes et a conferer au cryostat la plus grande autonomie possible. L'enceinte experimentale situee en general dans la partie inferieure de l'appareil necessite dans tous les cas une etude speciale. D'autre part des ensembles complets tels que les cannes de transfert, piege isole, robinet pour vide secondaire, ont ete concus dans le meme souci de rentabilite et de standardisation. Ce materiel peut donc repondre a un grand nombre d'exigences experimentales, il est facilement adaptable, et les consommations d'helium et d'azote liquide sont tres reduites. (auteurs)

  7. Circumcision revision in male children

    Directory of Open Access Journals (Sweden)

    Mohammed A. Al-Ghazo

    2006-08-01

    Full Text Available OBJECTIVE: To determine indications for circumcision revision and to identify the specialty of the person who performed unsatisfactory primary circumcision. MATERIALS AND METHODS: The authors reviewed medical records of 52 cases that underwent circumcision revision over a 6-year period (1998 to 2004. Sleeve surgical technique was used for revision in patients with redundant foreskin or concealed penis, penoplasty for partial or complete degloving of the penis and meatotomy for external meatal stenosis. The mean age of children was 32 months (range 6 months to 9 years. RESULTS: Most of unsatisfactory primary circumcisions (86.7% were performed by laymen. All patients who underwent circumcision revision had good to excellent cosmetic results. CONCLUSION: Primary circumcision performed by laymen carry a high complication rate and serious complications may occur. A period of training and direct supervision by physicians is required before allowing laymen to perform circumcision independently.

  8. Corporate Author Entries. Revision 5

    International Nuclear Information System (INIS)

    Hendricks, P.L.

    1986-05-01

    This reference authority has been created and is maintained to provide standard forms for recording the names of organizations consistently in bibliographic citations. This revision includes approximately 42,000 entries established since 1973

  9. [Penicher: an manuscript addendum to his pharmacopoeia of 1695 on the copy of Pharmacy College Library].

    Science.gov (United States)

    Bonnemain, Bruno

    2016-03-01

    Penicher's pharmacopeia (1695) was part of the Library of the "College de Pharmacie". The inventory of this Library was done in 1780 and is kept by the Library of the BIU Santé, Paris-Descartes University in Paris that digitized it recently. This copy contains handwritten texts that complete the original edition. The first main addition, at the beginning of the document, is three recipes of drugs, in Latin, one of them being well known at the early 18th century, the vulnerary balm of Leonardo Fioraventi (1517-1588), that is also known as Fioraventi's alcoholate. This product will still be present in the French Codex until 1949. The Penicher' book also includes, at the end, three handwritten pages in French which represent the equipment of apothecaries. These drawings are very close to the ones of Charas' Pharmacopeia. One can think that these additions are from the second part of the 18th century, but before the gift of the pharmacopeia to the College de Pharmacie by Fourcy en 1765. The author is unknown but he is probably one of the predecessor of Fourcy in Pharmacie de l'Ours (Bear's pharmacy). This gift done by Fourcy when joining the Community of Parisians pharmacists did not prevent the fact that Fourcy was sentenced by his colleagues pharmacists, a few years later, for the sales of "Chinese specialties" that someone called Jean-Daniel Smith, a physician installed in Paris, asked him to prepare.

  10. Symposium on international safeguards: Verification and nuclear material security. Book of extended synopses. Addendum

    International Nuclear Information System (INIS)

    2001-01-01

    The symposium covered the topics related to international safeguards, verification and nuclear materials security, namely: verification and nuclear material security; the NPT regime: progress and promises; the Additional Protocol as an important tool for the strengthening of the safeguards system; the nuclear threat and the nuclear threat initiative. Eighteen sessions dealt with the following subjects: the evolution of IAEA safeguards ( including strengthened safeguards, present and future challenges; verification of correctness and completeness of initial declarations; implementation of the Additional Protocol, progress and experience; security of material; nuclear disarmament and ongoing monitoring and verification in Iraq; evolution of IAEA verification in relation to nuclear disarmament); integrated safeguards; physical protection and illicit trafficking; destructive analysis for safeguards; the additional protocol; innovative safeguards approaches; IAEA verification and nuclear disarmament; environmental sampling; safeguards experience; safeguards equipment; panel discussion on development of state systems of accountancy and control; information analysis in the strengthened safeguard system; satellite imagery and remote monitoring; emerging IAEA safeguards issues; verification technology for nuclear disarmament; the IAEA and the future of nuclear verification and security

  11. 29 CFR 1926.952 - Mechanical equipment.

    Science.gov (United States)

    2010-07-01

    ... equipment that are not covered with insulating protective equipment. (c) Derrick trucks, cranes and other lifting equipment. (1) All derrick trucks, cranes and other lifting equipment shall comply with subpart N...

  12. 22 CFR 135.32 - Equipment.

    Science.gov (United States)

    2010-04-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  13. 21 CFR 1403.32 - Equipment.

    Science.gov (United States)

    2010-04-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  14. 45 CFR 602.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  15. 49 CFR 18.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  16. 34 CFR 80.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  17. 10 CFR 600.232 - Equipment.

    Science.gov (United States)

    2010-01-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  18. 45 CFR 1183.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

  19. Environmental Technology Verification Coatings and Coating Equipment Program (ETV CCEP). High Transfer Efficiency Spray Equipment - Generic Verification Protocol (Revision 0)

    Science.gov (United States)

    2006-09-30

    High-Pressure Waterjet • CO2 Pellet/Turbine Wheel • Ultrahigh-Pressure Waterjet 5 Process Water Reuse/Recycle • Cross-Flow Microfiltration ...documented on a process or laboratory form. Corrective action will involve taking all necessary steps to restore a measuring system to proper working order...In all cases, a nonconformance will be rectified before sample processing and analysis continues. If corrective action does not restore the

  20. Food Service Equipment and Appurtenances.

    Science.gov (United States)

    National Sanitation Foundation, Ann Arbor, MI.

    Equipment design specifications are presented relating to tables of all kinds, counters, sinks and drainboards, bins, shelves, drawers, hoods and similar kitchen appurtenances, not including baking, roasting, toasting, broiling or frying equipment, food preparation machinery such as slicers, choppers, and cutters, mixers and grinders, steam…

  1. 75 FR 63 - Hazardous Materials: Revision to Requirements for the Transportation of Batteries and Battery...

    Science.gov (United States)

    2010-01-04

    ... contained in equipment, fuel cell systems must not charge batteries during transport; (3) For transportation... 2137-AE54 Hazardous Materials: Revision to Requirements for the Transportation of Batteries and Battery... batteries and battery-powered devices. This final rule corrects several errors in the January 14, 2009 final...

  2. Equipe de trabalho

    Directory of Open Access Journals (Sweden)

    Gabriel Gerber Hornink

    2014-08-01

    Full Text Available   Equipe de Trabalho 2014 1. Equipe editorial Editor-Chefe Bayardo Bapstista Torres, Instituto de Química - USP, Brasil Eduardo Galembeck, Departamento de Bioquímica Instituto de Biologia UNICAMP, Brasil   Editores Gabriel Gerber Hornink, Depto. Bioquímica, Instituto de Ciências Biomédicas, Universidade - Federal de Alfenas - Unifal-MG, Brasil Vera Maria Treis Trindade, Instituto de Ciências Básicas da Saúde, Departamento de Bioquímica, Universidade Federal do Rio Grande do Sul, Brasil   Corpo Editorial Adriana Cassina, Departamento de Bioquímica, Facultad de Medicina, Universidad de la República, Uruguai Angel Herráez, Departamento de Bioquímica y Biología molecular, Universidad de Alcalá de Henares, Madrid, Espanha André Amaral Gonçalves Bianco, Universidade Federal de São Paulo (Unifesp, Brasil Denise Vaz de Macedo, Departamento de Bioquímica, Instituto de Biologia, Universidade Estadual de Campinas - Unicamp, Brasil Eneida de Paula, Departamento de Bioquímica, Instituto de Biologia, Universidade Estadual de Campinas - Unicamp, Brasil Guilherme Andrade Marson, Instituto de Química - USP, Brasil Jose Antonio Martinez Oyanedel, Universidad de Concepción, Chile Josep Maria Fernández Novell, Dept. Bioquímica i Biologia Molecular Universitat de Barcelona, Espanha Leila Maria Beltramini, Instituto de Física de São Carlos, Universidade Estadual de São Paulo - USP, Brasil Manuel João da Costa, Escola de Ciências da Saúde, Universidade do Minho, Portugal Maria Lucia Bianconi, Instituto de Bioquímica Médica Universidade Federal do Rio de Janeiro (UFRJ, Brasil María Noel Alvarez, Departamento de Bioquímica, Facultad de Medicina, Universidad de la República, Uruguai Miguel Ángel Medina Torres, Department of Molecular Biology & Biochemistry Faculty of Sciences University of Málaga, Espanha Nelma Regina Segnini Bossolan, Instituto de Física de São Carlos, Universidade de São Paulo - USP, Brasil Paulo De Avila

  3. Impact of receipt of coprocessed uranium/plutonium on advanced accountability concepts and fabrication facilities. Addendum 1 to application of advanced accountability concepts in mixed oxide fabrication

    International Nuclear Information System (INIS)

    Bastin, J.J.; Jump, M.J.; Lange, R.A.; Randall, C.C.

    1977-11-01

    The Phase I study of the application of advanced accountability methods (DYMAC) in a uranium/plutonium mixed oxide facility was extended to assess the effect of coprocessed UO 2 --PuO 2 feed on the observations made in the original Phase I effort and on the proposed Phase II program. The retention of plutonium mixed with uranium throughout the process was also considered. This addendum reports that coprocessed feed would have minimal effect on the DYMAC program, except in the areas of material specifications, starting material delivery schedule, and labor requirements. Each of these areas is addressed, as are the impact of coprocessed feed at a large fuel fabrication facility and the changes needed in the dirty scrap recovery process to maintain the lower plutonium levels which may be required by future nonproliferation philosophy. An amended schedule for Phase II is included

  4. Information technology equipment cooling method

    Science.gov (United States)

    Schultz, Mark D.

    2015-10-20

    According to one embodiment, a system for removing heat from a rack of information technology equipment may include a sidecar indoor air to liquid heat exchanger that cools air utilized by the rack of information technology equipment to cool the rack of information technology equipment. The system may also include a liquid to liquid heat exchanger and an outdoor heat exchanger. The system may further include configurable pathways to connect and control fluid flow through the sidecar heat exchanger, the liquid to liquid heat exchanger, the rack of information technology equipment, and the outdoor heat exchanger based upon ambient temperature and/or ambient humidity to remove heat generated by the rack of information technology equipment.

  5. WHO position on the use of fractional doses - June 2017, addendum to vaccines and vaccination against yellow fever WHO: Position paper - June 2013.

    Science.gov (United States)

    World Health Organization

    2017-10-13

    This article presents the World Health Organization's (WHO) recommendations on the use of fractional doses of yellow fever vaccines excerpted from the "Yellow fever vaccine: WHO position on the use of fractional doses - June 2017, Addendum to Vaccines and vaccination against yellow fever WHO: Position Paper - June 2013″, published in the Weekly Epidemiological Record [1,2]. This addendum to the 2013 position paper pertains specifically to use of fractional dose YF (fYF) vaccination (fractional dose yellow fever vaccination refers to administration of a reduced volume of vaccine dose, which has been reconstituted as usual per manufacturer recommendations) in the context of YF vaccine supply shortages beyond the capacity of the global stockpile. The current WHO position on the use of yellow fever (YF) vaccine is set out in the 2013 WHO position paper on vaccines and vaccination against YF and those recommendations are unchanged. Footnotes to this paper provide a number of core references including references to grading tables that assess the quality of the scientific evidence, and to the evidence-to-recommendation table. In accordance with its mandate to provide guidance to Member States on health policy matters, WHO issues a series of regularly updated position papers on vaccines and combinations of vaccines against diseases that have an international public health impact. These papers are concerned primarily with the use of vaccines in large-scale immunization programmes; they summarize essential background information on diseases and vaccines, and conclude with WHO's current position on the use of vaccines in the global context. Recommendations on the use of Yellow Fever vaccines were discussed by SAGE in October 2016; evidence presented at these meetings can be accessed at: www.who.int/immunization/sage/meetings/2016/October/presentations_background_docs/en/. Copyright © 2017. Published by Elsevier Ltd.

  6. HFBR restart activity A2.6: Review of FSAR and 60 MW addendum to assure consistency of operation at 40 MW

    International Nuclear Information System (INIS)

    Rao, D.V.; Ross, S.B.; Darby, J.L.; Clark, R.A.

    1990-01-01

    The purpose of this task (HFBR Restart Activity A2.6) is to perform a review of the design basis accident (DBA) analyses sections of the 1964 HFBR-Final Safety Analysis Report; Volumes I and II, and the 1982 Addendum to the HFBR-FSAR for 60 MW operation to assure that operation at 40 MW will be consistent with these analyses. Additional documents utilized in the review included the Level 1 PRA for HFBR, HFBR-PDMs and HFBR-OPMs. The review indicates that the 1964 FSAR-DBA analysis in incomplete in the sense that it did not analyze some of the important initiators for 1-loop operation that include: Accidental throttling of primary flow control valves; seizure of primary pump; loss of secondary pump; accidental throttling of secondary flow control valves; rupture of secondary piping. The first three initiators were later studied in the 1982 addendum. The other two initiators have not been examined to-date for 1-loop operation. It is recommended that the impact of these initiators be assessed prior to the restart, if 1-loop operation is chosen for the restart. The review demonstrated that at 40 MW operation there are only a few accident initiators that will culminate in core damage (fuel melting and /or cladding failure) regardless of the availability of mitigating systems. For 1-loop Operation these accidents include: Fuel channel blockage, primary pump seizure, and large-large LOCA (a LOCA with effective break diameter > 2.81 in. is referred to as a large-large LOCA in this document as well as in PRA). Although all these accidents listed above could lead to core damage for 1-loop operation as well, the probability is expected be very low

  7. The Role of the Inspector during an Emergency. Addendum to the Inspection of Emergency Arrangements [NEA/CNRA/R(2013)2

    International Nuclear Information System (INIS)

    Veyret, Olivier; Kupila, Jukka

    2015-06-01

    A fundamental goal in a regulatory authority's oversight of nuclear facilities is to establish confidence that adequate arrangements are in place for emergency preparedness and response. The CNRA published a report in 1998 on the inspection of licensee activities in emergency planning [NEA/CNRA/R(98)2]. Significant changes have occurred in the interim period, including early lessons learnt from the Fukushima accident. Therefore, the WGIP determined that it would be prudent for member countries to share good inspection practices associated with emergency arrangements (preparedness and response) in an updated report. In December 2013, the WGIP therefore presented the report entitled Inspection of Emergency Arrangements [NEA/CNRA/R(2013)2] for CNRA approval. While the report was approved at the December 2013 CNRA meeting, members requested that a short addendum be developed to compile member countries experiences of the role of the inspector during an emergency. The present addendum to NEA/CNRA/R(2013)2 identifies six additional commendable practices. The WGIP generated a questionnaire to address aspects of the role of the inspector during an emergency. Details of the questions posed to WGIP members are set out in Section 3 of this report. The following twenty countries responded to the questionnaire: Belgium, Canada, Czech Republic, Finland, France, Germany, India, Italy, Japan, Korea, Mexico, the Netherlands, Russia, Slovak Republic, Slovenia, Spain, Sweden, Switzerland, United Kingdom and United States. The WGIP members were requested to response concisely to the two main questions in the questionnaire. Appendix A provides the detailed responses to the questions. Appendix B includes supplementary information provided by several countries. An analysis of WGIP members' responses is presented in Section 4 of this report and conclusions are presented in Section 5

  8. Conceptual design report for a remotely operated cask handling system. Revision 1

    International Nuclear Information System (INIS)

    Yount, J.A.; Berger, J.D.

    1984-09-01

    Recent advances in remote handling utilizing commercial robotics are conceptually applied to lowering operator cumulative radiation exposure and increasing throughput during cask handling operations in nuclear shipping and receiving facilities. Revision 1 incorporates functional criteria for facility equipment, equipment technical outline specifications, and interface control drawings to assist Architect Engineers in the application of remote handling to waste shipping and receiving facilities. The document has also been updated to show some of the equipment used in proof-of-principle testing during fiscal year 1984. 10 references, 50 figures, 1 table

  9. Development of manufacturing equipment and QC equipment for DUPIC fuel

    International Nuclear Information System (INIS)

    Yang, Myung Seung; Park, J.J.; Lee, J.W.; Kim, S.S.; Yim, S.P.; Kim, J.H.; Kim, K.H.; Na, S.H.; Kim, W.K.; Shin, J.M.; Lee, D.Y.; Cho, K.H.; Lee, Y.S.; Sohn, J.S.; Kim, M.J.

    1999-05-01

    In this study, DUPIC powder and pellet fabrication equipment, welding system, QC equipment, and fission gas treatment are developed to fabricate DUPIC fuel at IMEF M6 hot cell. The systems are improved to be suitable for remote operation and maintenance with the manipulator at hot cell. Powder and pellet fabrication equipment have been recently developed. The systems are under performance test to check remote operation and maintenance. Welding chamber and jigs are designed and developed to remotely weld DUPIC fuel rod with manipulators at hot cell. Remote quality control equipment are being tested for analysis and inspection of DUPIC fuel characteristics at hot cell. And trapping characteristics is analyzed for cesium and ruthenium released under oxidation/reduction and sintering processes. The design criteria and process flow diagram of fission gas treatment system are prepared incorporating the experimental results. The fission gas treatment system has been successfully manufactured. (Author). 33 refs., 14 tabs., 91 figs

  10. TRANSPORT AND EMPLACEMENT EQUIPMENT DESCRIPTIONS

    International Nuclear Information System (INIS)

    1997-01-01

    The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) Transport and Emplacement in the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. The Transport and Emplacement equipment described in this document consists of the following: (1) WP Transporter; (2) Reusable Rail Car; (3) Emplacement Gantry; (4) Gantry Carrier; and (5) Transport Locomotive

  11. Containment and Surveillance Equipment Compendium

    International Nuclear Information System (INIS)

    Luetters, F.O.

    1980-02-01

    The Containment and Surveillance Equipment Compendium contains information sections describing the application and status of seals, optical surveillance systems, and monitors for international safeguards systems. The Compendium is a collection of information on equipment in use (generally by the IAEA) or under development in the US in diverse programs being conducted at numerous facilities under different sponsors. The Compendium establishes a baseline for the status and applications of C/S equipment and is a tool to assist in the planning of future C/S hardware development activities. The Appendix contains design concepts which can be developed to meet future goals

  12. Analysis of Medical Equipment Management in Relation to the Mandatory Medical Equipment Safety Manager (MESM in Japan

    Directory of Open Access Journals (Sweden)

    Kai Ishida

    2014-01-01

    Full Text Available Half a decade has passed since the fifth revision of the medical law and mandatory appointment of a medical equipment safety manager (MESM in hospitals in Japan. During this period, circumstances have changed regarding maintenance of medical equipment (ME. We conducted a survey to examine these changes and the current situation in ME management. Maintenance of ME and related work were found to have increased in many hospitals, but the number of clinical engineering technologists (CETs has only slightly increased. The appointed MESM was a CET or physician in most hospitals. In hospitals where physicians were appointed as the MESM, 81% had operation managers. Many respondents commented that it was difficult for one person to cover all the tasks required by the MESM, due to a lack of knowledge, too much work, or other reasons. This suggests the importance of an operation manager for ME to work under the MESM.

  13. Revised radiation emergency procedures at Pakistan research reactor PINSTECH

    International Nuclear Information System (INIS)

    Orfi, S.D.; Javed, M.; Ahmad, S.; Akhtar, K.M.; Mubarak, M.A.

    1984-12-01

    Necessary procedures have been laid down in this report to meet the radiation emergency at Pakistan Research Reactor PINSTECH. The Nuclear Safety Committee PINSTECH (NSCP) had also recommended a number of improvements in the existing procedures. Revision of the procedures was also considered necessary to incorporate into it new radiation units/limits and new emergency equipment available. Radiation emergency preparedness programme is of continuous nature. Latest developments else-where and local experience contribute to the improvement of the existing arrangements under this programme. (A.B.)

  14. Revised licensee event report system

    International Nuclear Information System (INIS)

    Mays, G.T.; Poore, W.P.

    1985-01-01

    Licensee Event Reports (LERs) provide the basis for evaluating and assessing operating experience information from nuclear power plants. The reporting requirements for submitting LERs to the Nuclear Regulatory Commission have been revised. Effective Jan. 1, 1984, all events were to be submitted in accordance with 10 CFR 50.73 of the Code of Federal Regulations. Report NUREG-1022, Licensee Event Report System-Description of System and Guidelines for Reporting, describes the guidelines on reportability of events. This article summarizes the reporting requirements as presented in NUREG-1022, high-lights differences in data reported between the revised and previous LER systems, and presents results from a preliminary assessment of LERs submitted under the revised LER reporting system

  15. Data Center Equipment Location and Monitoring System

    DEFF Research Database (Denmark)

    2013-01-01

    Abstract: Data center equipment location systems include hardware and software to provide information on the location, monitoring, and security of servers and other equipment in equipment racks. The systems provide a wired alternative to the wireless RFID tag system by using electronic ID tags...... connected to each piece of equipment, each electronic ID tag connected directly by wires to an equipment rack controller on the equipment rack. The equipment rack controllers link to a central control computer that provides an operator ...

  16. EAS Equipment Authorization Grantee Registrations

    Data.gov (United States)

    Federal Communications Commission — EAS (Equipment Authorization System). Radio Frequency (RF) devices are required to be properly authorized under 47 CFR Part 2 prior to being marketed or imported...

  17. ENERGY STAR Certified Imaging Equipment

    Data.gov (United States)

    U.S. Environmental Protection Agency — Certified models meet all ENERGY STAR requirements as listed in the Version 2.0 ENERGY STAR Program Requirements for Imaging Equipment that are effective as of...

  18. EMR Measurements on NDA Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Macdonell, Alexander Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Meierbachtol, Krista Cruse [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Evans, James Walter Jr. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mayo, Douglas R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-07-10

    Electromagnetic radiation (EMR) emission strength measurements were performed on a suite of passive non-destructive assay (NDA) radiation detection equipment. Data were collected from 9 kHz up to 6 GHz on each of the assembled systems.

  19. Mongolia - Vocational Education - Equipment Upgrades

    Data.gov (United States)

    Millennium Challenge Corporation — Evaluation design The impact evaluation sought to identify the causal impact of exposure to equipment upgrades on subsequent outcomes. Insofar as we were not able to...

  20. Operation monitor for plant equipment

    International Nuclear Information System (INIS)

    Kondo, Tetsufumi; Kanemoto, Shigeru.

    1991-01-01

    In a nuclear power plant, states of each of equipment in the plant are monitored accurately even under such a operation condition that the power is changed. That is, the fundamental idea is based on a model comparison method. A deviation between an output signal upon normal plant state obtained in a forecasting model device and that of the objective equipment in the plant are compared with a predetermined value. The result of the comparison is inputted to an alarm device to alarm the abnormality of the states of the equipment to an operator. The device of the present invention thus constituted can monitor the abnormality of the operation of equipment accurately even under such a condition that a power level fluctuates. As a result, it can remarkably contribute to mitigate operator's monitoring operation under the condition such as during load following operation. (I.S.)

  1. Equipment improvements for performance enhancement

    International Nuclear Information System (INIS)

    Gaestel, P.; Guesnon, H.; Sauze, G.

    1994-01-01

    In order to enhance the reactor availability, several improvements on reactor equipment have been developed: design optimization for stator maintenance replacement in the main alternator; adjustment modification of stator coils in the main alternator for an easier maintenance; improvement of the fuel handling line (pole crane, transfer equipment, loading machine); development of a loose part trapping system in the steam generator secondary circuit. 1 tab

  2. Low level photoneutron detection equipment

    International Nuclear Information System (INIS)

    Ji Changsong; Zhang Yuqin; Li Yuansui

    1991-01-01

    A low level photoneutron detection equipment has been developed. The photoneutrons produced by interaction of 226 Ra gamma quanta and deutron (D) target are detected with n-n discrimination detector made up of 3 He proportional counter array. The D-content information in the target can be obtained from the measured photoneutron counts. The equipment developed is mainly used for nondestructive D-content measurement of D-devices

  3. FUSRAP equipment concept development study

    International Nuclear Information System (INIS)

    Hinerman, K.B.; Smith, R.E.

    1981-01-01

    Under DOE contract, Dalton-Dalton-Newport, Inc. is performing an engineering evaluation of three selected FUSRAP sites in an effort to generate equipment concepts to perform remedial action for retrieval, packaging, storing, and transporting contaminated soil and other debris. Along with this engineering evaluation, an analysis of state and Federal regulations was made which had significant impact on the selected equipment and costs for each remedial action concept

  4. Remotely operated replaceable process equipment

    International Nuclear Information System (INIS)

    Westendorf, H.

    1987-01-01

    The coupling process of pneumatic and electrical auxiliary lines of a pneumatic control pressure line in a large cell of the reprocessing plant is carried out, together with the coupling process of the connecting flange of the process equipment. The coupling places of the auxiliary lines, such as control or supply lines, are laid in the flange parts of the flanges to be connected. The pipe flange on the frame side remains flush with the connecting flange of the process equipment. (DG) [de

  5. Partners in qualified equipment supply

    International Nuclear Information System (INIS)

    Rygg, D.E.; O'Hare, G.J.

    1993-01-01

    Industry initiatives have been taken to improve procurement practices and commercial dedication programs, formation of procurement engineering groups, emphasis on product quality, and increased engineering involvement in procurement and maintenance of qualified equipment. This poses new challenges for many licensees in terms of resources, product knowledge, and access to information normally held proprietary by equipment suppliers. Alternative approaches to future licensee/Westinghouse relationships which will allow licensees to adapt to the changing environment are discussed. 2 figs

  6. Quantum interaction. Revised selected papers

    Energy Technology Data Exchange (ETDEWEB)

    Song, Dawei; Zhang, Peng; Wang, Lei [Aberdeen Univ. (United Kingdom). School of Computing; Melucci, Massimo [Padua Univ., Padova (Italy). Dept. of Information Engineering; Frommholz, Ingo [Bedfordshire Univ. (United Kingdom); Arafat, Sachi (eds.) [Glasgow Univ. (United Kingdom). School of Computing Science

    2011-07-01

    This book constitutes the thoroughly refereed post-conference proceedings of the 5th International Symposium on Quantum Interaction, QI 2011, held in Aberdeen, UK, in June 2011. The 26 revised full papers and 6 revised poster papers, presented together with 1 tutorial and 1 invited talk were carefully reviewed and selected from numerous submissions during two rounds of reviewing and improvement. The papers show the cross-disciplinary nature of quantum interaction covering topics such as computation, cognition, mechanics, social interaction, semantic space and information representation and retrieval. (orig.)

  7. HEDR modeling approach: Revision 1

    International Nuclear Information System (INIS)

    Shipler, D.B.; Napier, B.A.

    1994-05-01

    This report is a revision of the previous Hanford Environmental Dose Reconstruction (HEDR) Project modeling approach report. This revised report describes the methods used in performing scoping studies and estimating final radiation doses to real and representative individuals who lived in the vicinity of the Hanford Site. The scoping studies and dose estimates pertain to various environmental pathways during various periods of time. The original report discussed the concepts under consideration in 1991. The methods for estimating dose have been refined as understanding of existing data, the scope of pathways, and the magnitudes of dose estimates were evaluated through scoping studies

  8. Quantum interaction. Revised selected papers

    International Nuclear Information System (INIS)

    Song, Dawei; Zhang, Peng; Wang, Lei; Arafat, Sachi

    2011-01-01

    This book constitutes the thoroughly refereed post-conference proceedings of the 5th International Symposium on Quantum Interaction, QI 2011, held in Aberdeen, UK, in June 2011. The 26 revised full papers and 6 revised poster papers, presented together with 1 tutorial and 1 invited talk were carefully reviewed and selected from numerous submissions during two rounds of reviewing and improvement. The papers show the cross-disciplinary nature of quantum interaction covering topics such as computation, cognition, mechanics, social interaction, semantic space and information representation and retrieval. (orig.)

  9. Medical writing, revising and editing

    DEFF Research Database (Denmark)

    Pilegaard, Morten

    2006-01-01

    The globalization of science makes medical writing, editing and revision a rapidly growing field of linguistic study and practice. Medical science texts are written according to uniform, general guidelines and medical genres have become highly conventionalized in terms of structure and linguistic...... form. Medical editing often takes the form of peer review and mainly addresses issues of contents and overall validity. Medical revision incorporates the checking of the macrostructure and the microstructure of the text, its language and style and its suitability for the target reader or client...

  10. Revising Nabokov Revising”

    Directory of Open Access Journals (Sweden)

    Marie Bouchet

    2010-10-01

    Full Text Available Nabokov revised his works as he translated them and, on another plane, canon revisionism has been having its backlash and provoked other refracting waves. The purpose of the conference was to advance Nabokov studies through the discussion of how our view of Nabokov’s standing and his works today should be revised, especially after the publication of The Original of Laura. However the conference was not confined to just this theme, since “revising” is a word rich with implications. To borrow s...

  11. SU-G-TeP2-03: Comparison of Standard Dosimetry Protocol in Japan and AAPM TG-51 Addendum in Order to Establish Optimal Dosimetry for FFF Beam

    Energy Technology Data Exchange (ETDEWEB)

    Matsunaga, T; Adachi, Y [Department of Radiology, Seirei Hamamatsu General Hospital, Hamamatsu, Shizuoka (Japan); Hayashi, N [Graduate School of Health Sciences, Fujita Health University, Tayoake, Aichi (Japan); Nozue, M [Department of Radiation Oncology, Seirei Hamamtsu General Hospital, Hamamatsu, Shizuoka (Japan)

    2016-06-15

    Purpose: Japan Standard Dosimetry of Absorbed dose to water in external beam radiotherapy (JSDP12) is widely used to measure radiation dose in radiotherapy. However, JSDP12 does not take flattening-filter-free (FFF) beam into consideration. In addition, JSDP12 applied TPR20,10 for dose quality index for photon beam. The purpose of this study is to compare JSDP12 with AAPM TG-51 addendum in order to establish optimal dosimetry procedure for FFF beam. Method: We evaluated the ion-recombination factor (ks) and the correction factor of radial beam profile (Prp) in FFF beam dosimetry. The ks was introduced by 2 voltages method and verified by Jaffe’s plot. The Prp was given by both film measurement and calculation of treatment planning system, and compared them. Next, we compared the dose quality indexes (kQ) between TPR20,10 method and PDD(10)x method. Finally we considered optimal dosimetry protocol for FFF photon beam using JSDP12 with referring TG-51 addendum protocols. The FFF photon beams of 6 MV (6X-FFF) and 10 MV (10X-FFF) from TrueBeam were investigated in this study. Results: The ks for 6X-FFF and 10X-FFF beams were 1.005 and 1.010, respectively. The Prp of 0.6 cc ionization chamber for 6X-FFF and 10X-FFF beams (Film, TPS) were (1.004, 1.008) and (1.005, 1.008), respectively. The kQ for 6X-FFF and 10X-FFF beams (JSDP12, TG-51 addendum) were (0.9950, 0.9947) and (0.9851, 0.9845), respectively. The most effective factor for uncertainty in FFF photon beam measurement was Prp for JSDP12 formalism. Total dosimetric differences between JSDP12 and TG-51 addendum for 6X-FFF and 10X-FFF were -0.47% and -0.73%, respectively. Conclusion: The total dosimetric difference between JSDP12 and TG-51 addendum was within 1%. The introduction of kQ given by JSDP is feasible for FFF photon beam dosimetry. However, we think Prp should be considered for optimal dosimetry procedure even if JSDP12 is used for FFF photon beam dosimetry.

  12. Failure of aseptic revision total knee arthroplasties.

    Science.gov (United States)

    Leta, Tesfaye H; Lygre, Stein Håkon L; Skredderstuen, Arne; Hallan, Geir; Furnes, Ove

    2015-02-01

    In Norway, the proportion of revision knee arthroplasties increased from 6.9% in 1994 to 8.5% in 2011. However, there is limited information on the epidemiology and causes of subsequent failure of revision knee arthroplasty. We therefore studied survival rate and determined the modes of failure of aseptic revision total knee arthroplasties. This study was based on 1,016 aseptic revision total knee arthroplasties reported to the Norwegian Arthroplasty Register between 1994 and 2011. Revisions done for infections were not included. Kaplan-Meier and Cox regression analyses were used to assess the survival rate and the relative risk of re-revision with all causes of re-revision as endpoint. 145 knees failed after revision total knee arthroplasty. Deep infection was the most frequent cause of re-revision (28%), followed by instability (26%), loose tibial component (17%), and pain (10%). The cumulative survival rate for revision total knee arthroplasties was 85% at 5 years, 78% at 10 years, and 71% at 15 years. Revision total knee arthroplasties with exchange of the femoral or tibial component exclusively had a higher risk of re-revision (RR = 1.7) than those with exchange of the whole prosthesis. The risk of re-revision was higher for men (RR = 2.0) and for patients aged less than 60 years (RR = 1.6). In terms of implant survival, revision of the whole implant was better than revision of 1 component only. Young age and male sex were risk factors for re-revision. Deep infection was the most frequent cause of failure of revision of aseptic total knee arthroplasties.

  13. 29 CFR 97.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

  14. 44 CFR 13.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

  15. 24 CFR 85.32 - Equipment.

    Science.gov (United States)

    2010-04-01

    ...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

  16. 41 CFR 105-71.132 - Equipment.

    Science.gov (United States)

    2010-07-01

    .... (4) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be... managing equipment (including replacement equipment), whether acquired in whole or in part with grant funds... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Equipment. 105-71.132...

  17. 43 CFR 12.72 - Equipment.

    Science.gov (United States)

    2010-10-01

    ...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

  18. 1968 Listing of Swimming Pool Equipment.

    Science.gov (United States)

    National Sanitation Foundation, Ann Arbor, MI. Testing Lab.

    An up-to-date listing of swimming pool equipment including--(1) companies authorized to display the National Sanitation Foundation seal of approval, (2) equipment listed as meeting NSF swimming pool equipment standards relating to diatomite type filters, (3) equipment listed as meeting NSF swimming pool equipment standard relating to sand type…

  19. The nuclear liability conventions revised

    International Nuclear Information System (INIS)

    Reyners, P.

    2004-01-01

    The signature on 12 February 2004 of the Protocols amending respectively the 1960 Paris Convention and the 1963 Brussels Supplementary Convention was the second step of the process of modernisation of the international nuclear liability regime after the adoption in September 1997 of a Protocol revising the 1963 Vienna Convention and of a new Convention on Supplementary Compensation for Nuclear Damage. The common objective of the new instruments is to provide more funds to compensate a larger number of potential victims in respect of a broader range of damage. Another goal of the revision exercise was to maintain the compatibility between the Paris and Vienna based systems, a commitment enshrined in the 1988 Joint Protocol, as well as to ascertain that Paris/Brussels countries could also become a Party to the Convention on Supplementary Compensation. However, while generally consistent vis a vis the Joint Protocol, the provisions of the Paris and Vienna Conventions, as revised, differ on some significant aspects. Another remaining issue is whether the improved international nuclear liability regime will succeed in attracting in the future a larger number of countries, particularly outside Europe, and will so become truly universal. Therefore, the need for international co-operation to address these issues, to facilitate the adoption of new implementing legislation and to ensure that this special regime keeps abreast of economic and technological developments, is in no way diminished after the revision of the Conventions.(author)

  20. Concise revision of the Sarcospermataceae

    NARCIS (Netherlands)

    Lam, H.J.; Royen, van P.

    1952-01-01

    After the senior writer, together with W. W. Varossieau, had published a revision of this monogeneric family (Blumea III, 1938—’39 and IV, 1941), some more material has been examined by us and, moreover, some new species have been described. Thanks to the courtesy of Prof. F. Gagnepain of Paris, and

  1. Guidelines for Curriculum Development. Revised.

    Science.gov (United States)

    Kistler, K.; And Others

    The curriculum development process explained in this booklet was first implemented at College of the Redwoods in May 1986 and then revised in June 1989. First, information on the college's Curriculum Committee is provided, indicating that the committee was formed to plan credit/non-credit courses; evaluate and approve additions, modifications, or…

  2. Revised Accounting for Business Combinations

    Science.gov (United States)

    Wilson, Arlette C.; Key, Kimberly

    2008-01-01

    The Financial Accounting Standards Board (FASB) has recently issued Statement of Financial Accounting Standards No. 141 (Revised 2007) Business Combinations. The object of this Statement is to improve the relevance, representational faithfulness, and comparability of reported information about a business combination and its effects. This Statement…

  3. How Adults Learn. Revised Edition.

    Science.gov (United States)

    Kidd, J. R.

    The book's emphasis is on learning during the years of adulthood and examines present-day practice of adult education for practitioners. This revised edition brings up to date advances in such areas of learning as controversial theory; the effects of environment; sensory processes; intellectual capacities; motivation and attitude; transactional…

  4. A revision of the Paronychiinae

    NARCIS (Netherlands)

    Chaudhri, Mohammad Nazeer

    1968-01-01

    This study was undertaken, in April 1964, at the suggestion of Prof. Dr. J. Lanjouw. The need for such a revision, was, however, stressed by the authors of the subtribe, viz. PAX et K. HOFFMANN, who, while delimiting these genera, remarked that the Systematics of both the (main) genera of this

  5. Diet History Questionnaire: Database Revision History

    Science.gov (United States)

    The following details all additions and revisions made to the DHQ nutrient and food database. This revision history is provided as a reference for investigators who may have performed analyses with a previous release of the database.

  6. [Revised practice guideline 'Anaemia in midwifery practice'

    NARCIS (Netherlands)

    Beentjes, M.; Jans, S.M.P.J.

    2012-01-01

    The practice guideline of the Royal Dutch Organization of Midwives 'Anaemia in primary care midwifery practice' published in 2000, has recently been revised. The revised guideline takes physiological haemodilution during pregnancy into consideration and provides gestation specific reference values

  7. Revised Human Health Risk Assessment on Chlorpyrifos

    Science.gov (United States)

    We have revised our human health risk assessment and drinking water exposure assessment for chlorpyrifos that supported our October 2015 proposal to revoke all food residue tolerances for chlorpyrifos. Learn about the revised analysis.

  8. 75 FR 60485 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2010-09-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2008-0497] NRC Enforcement Policy Revision AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement. SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is publishing a major revision to its Enforcement Policy (Enforcement Policy or Policy) to...

  9. Performance monitoring of safeguards equipment

    International Nuclear Information System (INIS)

    Sirisena, K.; Peltoranta, M.; Goussarov, V.; Vodrazka, P.

    1999-01-01

    SGTCS is responsible for monitoring and reporting the performance of the SG equipment. Performance monitoring (PM) has been implemented in most important safeguards equipment operating unattended in nuclear facilities. Inspectors acquire equipment performance data in facilities. After inspection, the data package is submitted to SGTCS for processing and analysis. The performance data is used for identification of systems or components, which should be changed in the field and for identification of modules which, should be diagnosed at HQ in order to determine the cause of failure. Moreover, the performance data is used for preventive maintenance and spares distribution planning, and to provide statistics for official reports and management decision making. An important part of the performance monitoring is reporting. Equipment performance reports contain information about equipment inventory, utilization, failure types, failure distribution, and reliability. Trends in performance are given in graphical form in cases, where past data is available. Reliability estimates such as expected times between failures are provided. The automated reporting tools are obtainable through EMIS database application. (author)

  10. AVM branch vibration test equipment

    International Nuclear Information System (INIS)

    Anne, J.P.

    1995-01-01

    An inventory of the test equipment of the AVM Branch ''Acoustic and Vibratory Mechanics Analysis Methods'' group has been undertaken. The purpose of this inventory is to enable better acquaintance with the technical characteristics of the equipment, providing an accurate definition of their functionalities, ad to inform potential users of the possibilities and equipment available in this field. The report first summarizes the various experimental surveys conduced. Then, using the AVM equipment database to draw up an exhaustive list of available equipment, it provides a full-scope picture of the vibration measurement systems (sensors, conditioners and exciters) and data processing resources commonly used on industrial sites and in laboratories. A definition is also given of a mobile test unit, called 'shelter', and a test bench used for the testing and performance rating of the experimental analysis methods developed by the group. The report concludes with a description of two fixed installations: - the calibration bench ensuring the requisite quality level for the vibration measurement systems ; - the training bench, whereby know-how acquired in the field in the field of measurement and experimental analysis processes is made available to others. (author). 27 refs., 15 figs., 2 appends

  11. Safeguards techniques and equipment. 2003 ed

    International Nuclear Information System (INIS)

    2003-01-01

    The 1990s saw significant non-proliferation related developments in the world, resulting in a new period of safeguards development. Over several years an assessment was made of how to strengthen the effectiveness and improve the efficiency of IAEA safeguards. In May 1997 this culminated in the adoption by the IAEA Board of Governors of a Protocol Additional to Safeguards Agreements which significantly broadens the role of IAEA safeguards. As a consequence, the IAEA safeguards system entered a new era. In 1997 the IAEA began to publish a new series of booklets on safeguards, called the International Nuclear Verification Series (NVS). The objective of these booklets was to help in explaining IAEA safeguards, especially the new developments in safeguards, particularly for facility operators and government officers involved with these topics. The current booklet, which is a revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. A completely new section on data security has been added to describe the specific features that are included in installed equipment systems in order to ensure the authenticity and confidentiality of information. As new verification measures continue to be developed the material in this booklet will be periodically reviewed and updated versions issued. The basic verification measure used by the IAEA is nuclear material accountancy. In applying nuclear material accountancy, IAEA safeguards inspectors make independent measurements to verify quantitatively the amount of nuclear material presented in the State's accounts. For this purpose, inspectors count items (e.g. fuel assemblies, bundles or rods, or containers of powdered compounds of uranium or plutonium) and measure attributes of these items during their inspections using non

  12. 78 FR 25916 - Authorization of Radiofrequency Equipment

    Science.gov (United States)

    2013-05-03

    ...] Authorization of Radiofrequency Equipment AGENCY: Federal Communications Commission. ACTION: Proposed rule... bodies, and measurement procedures used to determine RF equipment compliance. The Commission believes... Commission is responsible for an equipment authorization program for radiofrequency (RF) devices under part 2...

  13. Humeral windows in revision total elbow arthroplasty.

    Science.gov (United States)

    Peach, Chris A; Salama, Amir; Stanley, David

    2016-04-01

    The use of cortical windows for revision elbow arthroplasty has not previously been widely reported. Their use aids safe revision of a well fixed humeral prosthesis and can be used in the setting of dislocation, periprosthetic fracture or aseptic loosening of the ulnar component. We describe our technique and results of cortical windows in the distal humerus for revision elbow arthroplasty surgery.

  14. A taxonomic revision of the genus Podocarpus

    NARCIS (Netherlands)

    Laubenfels, de D.J.

    1985-01-01

    In connection with the forthcoming revision of the Coniferae for the Flora Malesiana, the author thought it necessary to revise the genus Podocarpus. Although this genus has a substantial representation in Malesia (30 species), the revision is too involved to be appropriate with the Flora Malesiana

  15. 24 CFR 968.225 - Budget revisions.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Budget revisions. 968.225 Section... Fewer Than 250 Units) § 968.225 Budget revisions. (a) A PHA shall not incur any modernization cost in excess of the total HUD-approved CIAP budget. A PHA shall submit a budget revision, in a form prescribed...

  16. 7 CFR 3015.115 - Budget revisions.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Budget revisions. 3015.115 Section 3015.115..., DEPARTMENT OF AGRICULTURE UNIFORM FEDERAL ASSISTANCE REGULATIONS Programmatic Changes and Budget Revisions § 3015.115 Budget revisions. (a) Nonconstruction projects. (1) Except as provided in paragraph (a)(2) of...

  17. 48 CFR 15.307 - Proposal revisions.

    Science.gov (United States)

    2010-10-01

    ... AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Source Selection 15.307 Proposal revisions. (a) If an... allow proposal revisions to clarify and document understandings reached during negotiations. At the... submit a final proposal revision. The contracting officer is required to establish a common cut-off date...

  18. Another donation of computer equipment

    CERN Multimedia

    Anaïs Schaeffer

    2014-01-01

    On Thursday 27 February, CERN was pleased to donate computer equipment to a physics institute in the Philippines.   H.E. Leslie J. Baja and Rolf Heuer. Following donations of computer equipment to institutes in Morocco, Ghana, Bulgaria, Serbia and Egypt, CERN is to send 50 servers and 4 network switches to the National Institute of Physics at the University of the Philippines Diliman. CERN’s Director-General Rolf Heuer and the Ambassador of the Philippines to Switzerland and Lichtenstein, H.E. Leslie J. Baja, spoke of their enthusiasm for the project during an official ceremony. The equipment will be used for various high energy physics research programmes in the Philippines and for the University’s development of digital resources for science.

  19. Preliminary hazards analysis of thermal scrap stabilization system. Revision 1

    International Nuclear Information System (INIS)

    Lewis, W.S.

    1994-01-01

    This preliminary analysis examined the HA-21I glovebox and its supporting systems for potential process hazards. Upon further analysis, the thermal stabilization system has been installed in gloveboxes HC-21A and HC-21C. The use of HC-21C and HC-21A simplified the initial safety analysis. In addition, these gloveboxes were cleaner and required less modification for operation than glovebox HA-21I. While this document refers to glovebox HA-21I for the hazards analysis performed, glovebox HC-21C is sufficiently similar that the following analysis is also valid for HC-21C. This hazards analysis document is being re-released as revision 1 to include the updated flowsheet document (Appendix C) and the updated design basis (Appendix D). The revised Process Flow Schematic has also been included (Appendix E). This Current revision incorporates the recommendations provided from the original hazards analysis as well. The System Design Description (SDD) has also been appended (Appendix H) to document the bases for Safety Classification of thermal stabilization equipment

  20. 75 FR 2796 - Revisions to the California State Implementation Plan, San Joaquin Valley Air Pollution Control...

    Science.gov (United States)

    2010-01-19

    ...EPA is finalizing approval of revisions to the San Joaquin Valley Air Pollution Control District portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on June 16, 2009 and concern volatile organic compound (VOC) emissions from coating of metal parts, large appliances, metal furniture, motor vehicles, mobile equipment, cans, coils, organic solvent cleaning, and storage and disposal related to such operations. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  1. Waste Electrical and Electronic Equipment

    DEFF Research Database (Denmark)

    Bigum, Marianne Kristine Kjærgaard; Christensen, Thomas Højlund

    2011-01-01

    Waste electrical and electronic equipment (WEEE) is one of the fastest growing special waste types with an estimated growth of 3–5% per year (Cui and Forssberg, 2003). WEEE is a very heterogeneous waste type that contains many compounds that are considered to be harmful to both humans and the env......Waste electrical and electronic equipment (WEEE) is one of the fastest growing special waste types with an estimated growth of 3–5% per year (Cui and Forssberg, 2003). WEEE is a very heterogeneous waste type that contains many compounds that are considered to be harmful to both humans...

  2. The development of superconducting equipment

    CERN Document Server

    Ueda, T; Hiue, H

    2003-01-01

    Fuji Electric has been developing various types of superconducting equipment for over a quarter of a century. This paper describes the development results achieved for superconducting equipment and especially focuses on large-capacity current leads and superconducting transmission systems, the development of which is being promoted for application to the field of nuclear fusion. High temperature superconductor (HTS) is becoming the mainstream in the field of superconductivity, and the HTS floating coil and conduction-cooled HTS transformed are also introduced as recent developments for devices that utilize this technology. (author)

  3. Mechanical (turbines and auxiliary equipment)

    CERN Document Server

    Sherry, A; Cruddace, AE

    2013-01-01

    Modern Power Station Practice, Volume 3: Mechanical (Turbines and Auxiliary Equipment) focuses on the development of turbines and auxiliary equipment used in power stations in Great Britain. Topics covered include thermodynamics and steam turbine theory; turbine auxiliary systems such as lubrication systems, feed water heating systems, and the condenser and cooling water plants. Miscellaneous station services, and pipework in power plants are also described. This book is comprised of five chapters and begins with an overview of thermodynamics and steam turbine theory, paying particular attenti

  4. ASSET guidelines. Revised 1991 Edition

    International Nuclear Information System (INIS)

    1991-12-01

    The present publication is an updated version of the IAEA Assessment of Safety Significant Events Team (ASSET) Guidelines, IAEA-TECDOC-573, published in 1990. Sections 5 and 6 include revised definitions and investigation guidelines for identification of both direct and root causes. These revisions were recommended by a Consultants Meeting held in Vienna on 3-7 December 1990. This guidance is not intended to infringe an expert's prerogative to investigate additional items. Its main purpose is to provide a basic structure and ensure consistency in the assessments. Use of the ASSET guidelines should also facilitate comparison between the observations made in different nuclear power plants and harmonize the reporting of generic ASSET results. The guidelines should always be used with a critical attitude and a view to possible improvements

  5. Damage limits of accelerator equipment

    CERN Document Server

    Rosell, Gemma

    2014-01-01

    Beam losses occur in particle accelerators for various reasons. The effect of lost particles on accelerator equipment becomes more severe with the increasing energies and intensities. The present study is focused on the damage potential of the proton beam as a function of particle energy and beam size. Injection and extraction energies of different accelerators at CERN were considered.

  6. Pocket dictionary of laboratory equipment

    International Nuclear Information System (INIS)

    Junge, H.D.

    1987-01-01

    This pocket dictionary contains the 2500 most common terms for scientific and technical equipment in chemical laboratories. It is a useful tool for those who are used to communicating in German and English, but have to learn the special terminology in this field. (orig.) [de

  7. Using Gaming Equipment to Teach

    Science.gov (United States)

    Curriculum Review, 2009

    2009-01-01

    Gaming equipment (such as Nintendo's Wii[TM]) is making its way to schools and classrooms. However, most of the discussion regarding how to use this technology and integrate it into lesson plans is happening in blogs on the Internet. An advocate of interactive media in the classroom, Dr. Dawn Hawkins, a faculty member for the Art Institute of…

  8. Isotope-equipped measuring instruments

    International Nuclear Information System (INIS)

    Miyagawa, Kazuo; Amano, Hiroshi

    1980-01-01

    In the steel industry, though the investment in isotope-equipped measuring instruments is small as compared with that in machinery, they play important role in the moisture measurement in sintering and blast furnaces, the thickness measurement in rolling process and others in automatic control systems. The economic aspect of the isotope-equipped measuring instruments is described on the basis of the practices in Kimitsu Works of Nippon Steel Corporation: distribution of such instruments, evaluation of economic effects, usefulness evaluation in view of raising the accuracy, and usefulness evaluation viewed from the failure of the isotope instruments. The evaluation of economic effects was made under the premise that the isotope-equipped measuring instruments are not employed. Then, the effects of raising the accuracy are evaluated for a γ-ray plate thickness gauge and a neutron moisture gauge for coke in a blast furnace. Finally, the usefulness was evaluated, assuming possible failure of the isotope-equipped measuring instruments. (J.P.N.)

  9. Hydraulic turbines and auxiliary equipment

    Energy Technology Data Exchange (ETDEWEB)

    Luo Gaorong [Organization of the United Nations, Beijing (China). International Centre of Small Hydroelectric Power Plants

    1995-07-01

    This document presents a general overview on hydraulic turbines and auxiliary equipment, emphasizing the turbine classification, in accordance with the different types of turbines, standard turbine series in China, turbine selection based on the basic data required for the preliminary design, general hill model curves, chart of turbine series and the arrangement of application for hydraulic turbines, hydraulic turbine testing, and speed regulating device.

  10. Trust Revision for Conflicting Sources

    Science.gov (United States)

    2017-02-01

    strategy is to first revise a priori trust assignments as a function of the degree of conflict, before the evidence is fused. This paper focuses on the...practical trust transitivity seems to be idiosyncratic for humans and animals, with no true analogue among non- living forms (and in the physical world ...visiting a foreign country Alice is looking for a restaurant where the locals go, because she would like to avoid places overrun by tourists. She meets a

  11. Clean Air Act. Revision 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-15

    This Reference Book contains a current copy of the Clean Air Act, as amended, and those regulations that implement the statute and appear to be most relevant to DOE activities. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. This Reference Book has been completely revised and is current through February 15, 1994.

  12. Revised dietary guidelines for Koreans.

    Science.gov (United States)

    Jang, Young Ai; Lee, Haeng Shin; Kim, Bok Hee; Lee, Yoonna; Lee, Hae Jeung; Moon, Jae Jin; Kim, Cho-il

    2008-01-01

    With rapidly changing dietary environment, dietary guidelines for Koreans were revised and relevant action guides were developed. First, the Dietary Guidelines Advisory Committee was established with experts and government officials from the fields of nutrition, preventive medicine, health promotion, agriculture, education and environment. The Committee set dietary goals for Koreans aiming for a better nutrition state of all after a thorough review and analysis of recent information related to nutritional status and/or problems of Korean population, changes in food production/supply, disease pattern, health policy and agricultural policy. Then, the revised dietary guidelines were proposed to accomplish these goals in addition to 6 different sets of dietary action guides to accommodate specific nutrition and health problems of respective age groups. Subsequently, these guidelines and guides were subjected to the focus group review, consumer perception surveys, and a public hearing for general and professional comments. Lastly, the language was clarified in terms of public understanding and phraseology. The revised Dietary guidelines for Koreans are as follows: eat a variety of grains, vegetables, fruits, fish, meat, poultry and dairy products; choose salt-preserved foods less, and use less salt when you prepare foods; increase physical activity for a healthy weight, and balance what you eat with your activity; enjoy every meal, and do not skip breakfast; if you drink alcoholic beverages, do so in moderation; prepare foods properly, and order sensible amounts; enjoy our rice-based diet.

  13. Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

    International Nuclear Information System (INIS)

    James, R.W.; Shank, J.W.; Yoder, C.

    1996-01-01

    Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

  14. Clarification of radiation-control regulations for diagnostic x-ray equipment

    International Nuclear Information System (INIS)

    1989-03-01

    The Office of Compliance and Surveillance of the Center for Devices and Radiological Health (CDRH) has received many requests for interpretation of the Federal regulations that relate to diagnostic x-ray equipment. Responses to these requests were originally issued as FDA Compliance Policy Guides, industry-wide letters, and letters to individuals. The document is a compilation of those responses that remain applicable. Guides or opinions that have been withdrawn or are now obsolete because they have been incorporated into the regulations are not included. The document consists of two sections: the General section, which contains information of a general nature; and the Specific section, which contains information specific to particular sections of the Federal Performance Standard for Diagnostic X-ray Equipment (21 CFR 1020.30-32). When the term 'Revised Language' appears in an item heading, it indicates English grammar correction; the term 'Revised' indicates an updated version of the original clarification

  15. Recent developments in methodology for dynamic qualification of nuclear plant equipment

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1984-01-01

    Dynamic qualification of nuclear plant electrical and mechanical equipment is performed basically under guidelines given in IEEE Standards 323 and 344, and a variety of NRC regulatory guides. Over the last fifteen years qualification methodology prescribed by these documents has changed significantly as interpretations, equipment capability, and imagination of the qualification engineers have progressed. This progress has been sparked by concurrent NRC and industry sponsored research programs that have identified anomalies and developed new methodologies for resolving them. Revisions of the standards have only resulted after a lengthy debate of all such new information and subsequent judgment of its validity. The purpose of this paper is to review a variety of procedural improvements and developments in qualification methodology that are under current consideration as revisions to the standards. Many of the improvements and developments have resulted from recent research programs. All are very likely to appear in one type of standard or another in the near future

  16. Dredging: An Annotated Bibliography on Operations, Equipment, and Processes. Installment 3. Revision.

    Science.gov (United States)

    1985-01-01

    recov- ery is several orders of magnitude slower than in temperate climates . Canada also has an "Environmental Assessment and Review Process," insti...factors such as climate , distance to disposal area, al range, wave period, minimum water depth, number of working shifts, port layout and physical...solved by g the Thoma-Moodt "similarity law" for the cavitation performance aulic pumps and turbines. Pertinent detailed definitions are d, followed by

  17. 78 FR 41434 - Proposed Revisions to Design of Structures, Components, Equipment and Systems

    Science.gov (United States)

    2013-07-10

    ... backfitting as defined in 10 CFR 50.109, or otherwise be inconsistent with the issue finality provisions in 10.... ADDRESSES: You may submit comments by any of the following methods (unless this document describes a.... You may access information related to this document, which the NRC possesses and is publicly available...

  18. 77 FR 14989 - Medicare Program; Revisions to the Durable Medical Equipment, Prosthetics, Orthotics, and...

    Science.gov (United States)

    2012-03-14

    ...), a skilled nursing facility (SNF), a comprehensive outpatient rehabilitation facility (CORF), a home..., a rehabilitation agency, or a public health agency that has in effect a similar agreement but only... for reduction of fractures and dislocations'' as one of the ``medical and other health services'' that...

  19. B and W NPGD quality assurance program for nuclear equipment. Revision 1

    International Nuclear Information System (INIS)

    1975-03-01

    B and W's Quality Assurance Program (QAP) is described. The program is implemented through the Nuclear Power Generation Division (NPGD) and includes design, procurement, and manufacturing activities of NPGD and all its suppliers furnishing items in the B and W scope of supply including other Divisions/ Subsidiaries of B and W. These activities are controlled by including applicable quality assurance requirements, as described, in NPGD procurement documents imposed on its suppliers. Each supplier must then establish and/or maintain a documented QA Program to meet the requirements imposed by the procurement documents. Implementation of the suppliers' NPGD-approved QA Program is verified by NPGD through Audit and QC Surveillance activities. The position and relationships of the NPGD within the Company's corporate structure are described. An overview of the QAP describing its implementation, its operation, the controls imposed on all suppliers (both corporate and vendor) and site consulting activities is presented. (U.S.)

  20. Revision to dedicated short range communication roadside equipment specification - RSU 4.1.Bench Test Plan.

    Science.gov (United States)

    2017-04-28

    The document describes the overall process for evaluating Dedicated Short Range Communication (DSRC) Roadside Units (RSU) against USDOT RSU Specification 4.1 in preparation for field evaluation. The Test Cases contained in this document only evaluate...

  1. 76 FR 18472 - Medicare Program; Revisions to the Durable Medical Equipment, Prosthetics, Orthotics, and...

    Science.gov (United States)

    2011-04-04

    ...) of the Act provides for the coverage of ``leg, arm, back, and neck braces, and artificial legs, arms... site at http://ecfr.gpoaccess.gov/cgi/t/text/text-idx?c=ecfr&sid=2465b064ba6965cc1fbd2eae60854b11&rgn=div8&view=text&node=13:1.0.1.1.16.1.266.9&idno=13 (refer to the 620000 series. There are four...

  2. Alternative Fuels Data Center: Biodiesel Equipment Options

    Science.gov (United States)

    Equipment Options to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Equipment Options on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Equipment Options on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Equipment Options on Google Bookmark Alternative Fuels

  3. 40 CFR 792.61 - Equipment design.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Equipment design. 792.61 Section 792.61...) GOOD LABORATORY PRACTICE STANDARDS Equipment § 792.61 Equipment design. Equipment used in the... of appropriate design and adequate capacity to function according to the protocol and shall be...

  4. 40 CFR 160.61 - Equipment design.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Equipment design. 160.61 Section 160... LABORATORY PRACTICE STANDARDS Equipment § 160.61 Equipment design. Equipment used in the generation... appropriate design and adequate capacity to function according to the protocol and shall be suitably located...

  5. 21 CFR 58.61 - Equipment design.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Equipment design. 58.61 Section 58.61 Food and... PRACTICE FOR NONCLINICAL LABORATORY STUDIES Equipment § 58.61 Equipment design. Equipment used in the... of appropriate design and adequate capacity to function according to the protocol and shall be...

  6. 34 CFR 74.34 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... as program income. (e) When acquiring replacement equipment, the recipient may use the equipment to... replacement equipment subject to the approval of the Secretary. (f) The recipient's property management... 34 Education 1 2010-07-01 2010-07-01 false Equipment. 74.34 Section 74.34 Education Office of the...

  7. 20 CFR 437.32 - Equipment.

    Science.gov (United States)

    2010-04-01

    ... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use.... Procedures for managing equipment (including replacement equipment), whether acquired in whole or in part... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Equipment. 437.32 Section 437.32 Employees...

  8. 45 CFR 2541.320 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... replacement equipment, the grantee or subgrantee may use the equipment to be replaced as a trade-in or sell... replacement equipment), whether acquired in whole or in part with grant funds, until disposition takes place... ensure the highest possible return. (e) Disposition. When original or replacement equipment acquired...

  9. 45 CFR 1174.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use... requirements. Procedures for managing equipment (including replacement equipment), whether acquired in whole or... original or replacement equipment acquired under a grant or subgrant is no longer needed for the original...

  10. 45 CFR 1157.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use... requirements. Procedures for managing equipment (including replacement equipment), whether acquired in whole or... original or replacement equipment acquired under a grant or subgrant is no longer needed for the original...

  11. The Cost of Maintaining Educational Communications Equipment.

    Science.gov (United States)

    Humphrey, David A.

    Tentative formulas for calculating the cost of maintaining educational communications equipment are proposed. The formulas are based on a survey of campuses of the State University of New York. The survey analyzed the types of equipment to be maintained, types of maintenance, who uses the equipment, who services the equipment, and the cost…

  12. Annual report of the group for maintenance of electrical equipment; Godisnji izvestaj elektro grupe

    Energy Technology Data Exchange (ETDEWEB)

    Rajic, M [Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis remontnih i revizionih radova na elektroopremi reaktora RA izvrsenih prema godisnjem planu u periodima kada reaktor nije radio. Vanplanski poslovi ukljucujuci popravke elektroopreme su takodje deo ovog izvestaja.

  13. Demand Response Potential for California SubLAPs and Local Capacity Planning Areas: An Addendum to the 2025 California Demand Response Potential Study – Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    Alstone, Peter [Humboldt State Univ., Arcata, CA (United States). Schatz Energy Research Center; Potter, Jennifer [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Piette, Mary Ann [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Schwartz, Peter [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Berger, Michael A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dunn, Laurel N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, Sarah J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sohn, Michael D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Aghajanzadeh, Arian [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Stensson, Sofia [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Szinai, Julia [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-04-01

    The 2025 California Demand Response Potential Study Phase 2 Report1 was released on March 1, 2017, and described a range of pathways for Demand Response (DR) to support a clean, stable, and cost-effective electric grid for California. One of the Report’s key findings was that while there appears to be very low future value for untargeted DR Shed aimed at system-wide peak load conditions, there could be significant value for locally focused Shed resources. Although the dynamics of renewable capacity expansion have reduced the pressure to build new thermal generation in general, there are still transmission-constrained areas of the state where load growth needs to be managed with the addition of new local capacity, which could include DERs and/or DR. This Addendum to the Phase 2 Report presents a breakdown of the expected future “Local Shed” DR potential at a finer geographic resolution than what is available in the original report, with results summarized by SubLAP and Local Capacity Area (LCA).

  14. Addendum to engineering evaluation/cost analysis for the proposed management of 15 nonprocess buildings (15 Series) at the Weldon Spring site chemical plant, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    MacDonell, M.M.; Peterson, J.M.

    1990-08-01

    An engineering evaluation/cost analysis (EE/CA) report was prepared in May 1989 to analyze alternatives for a proposed removal action to manage 15 nonprocess buildings, designated as the 15 Series buildings, at the chemical plant area of the Weldon Spring site. The alternative selected as a result of the analyses was to dismantle the buildings and to salvage or transport off-site for treatment or disposal all nonradioactively contaminated materials and to store on-site in a material staging area (MSA) all radioactively contaminated materials, pending a decision for disposal of all wastes resulting from remediation of the Weldon Spring site. Region VII of the US Environmental Protection Agency (EPA) and the state of Missouri concurred with the selection of this alternative and provided comments on the EE/CA report. The proposed removal action was not initiated at that time due to funding constraints. This addendum has been prepared to update information provided in the EE/CA report, provide additional information on the MSA, and respond to EPA Region VII and state of Missouri comments on the EE/CA. 5 refs., 1 tab

  15. Addendum 1 to CSER 96-025: PFP storage of 9.25/9.5 inch tall, 4.4 kg Pu cans on existing Vault 4 pedestals

    International Nuclear Information System (INIS)

    Hillesland, K.E.

    1997-01-01

    A nuclear criticality safety analysis has been performed to increase the approved plutonium mass limit for cans stored in Vault number-sign 4 cubicles at PFP. The original CSER 96-025 accommodated the storage of 4.4 kg of plutonium in PuO, (5.0 kg PuO,) in Vault number-sign 4 by requiring that half the cubicles be left vacant. This addendum allows for all the cubicles to be used, but with a fissile plutonium mass limit of 58 kg per cubicle. A mass limit for each cubical allows for storage of a larger number of cans if some have less than the 4.4 kg Pu limit per can. The highest k., calculated is 0.932 + 0.003 when an overbatched can is present in every fourth cubicle. This is below the criticality safety limit of kff 0.935, and consequently, an increase of plutonium mass to 4.4 kg per can is within acceptable safety limits for the given mass limit

  16. 78 FR 45017 - Amendment to the International Traffic in Arms Regulations: Revision of U.S. Munitions List...

    Science.gov (United States)

    2013-07-25

    ... the defense articles on the USML that are controlled by the Bureau of Alcohol, Tobacco, Firearms and...) Underwater single acoustic sensor system that distinguishes tonals and locates the origin of the sound; (iii... incorporating revision of USML Category XI]. (8) Unattended ground sensor (UGS) systems or equipment having all...

  17. The Variation Test and Extraction Equipment to Optimum Asphalt by Using Gasoline Solvent

    Science.gov (United States)

    Soehardi, Fitridawati

    2017-12-01

    Based on the Binamarga Specification 2010 at third revision, the extraction test should be carried out using the specimen from the loose asphalt mixture extracted from the back of the finisher bitumen machine. The purpose of this research is to find out the result of pretest and posttest extraction asphalt content. The Extraction test using two equipment, they are Soklet and Centrifuge. The specimens was used AMP, Asphalt Finisher and Core, which involved gasoline solvent. Based on the asphalt level extraction test results, the appropriate equipment was used centrifuge with the level accuracy as requirement of Binamarga Specification 2010 at third revision and the level of ease used as equipment in the field study. The asphalt content obtained for AMP 5,51%, Asphalt Finisher5,46% and Core 5.34%. As for the socket asphalt content obtained is AMP 5.55%, Asphalt Finisher 5.50% and Core core 5. 41%. The extract test value of asphalt content decreased, so it can be formulated KA JMF value of Job mix used was 5.56% with the tolerance given according to Binamarga Specification 2010 at third revision is ± 0.30%. In accordance with the results obtained then the results of a centrifuge tool that matches and meets the requirements of time, accuracy of results and economic value.

  18. HERCA Position Paper. The process of CT dose optimisation through education and training and role of CT Manufacturers - October 2014. Addendum to HERCA CT Position paper: The process of CT dose optimisation through education and training and the role of the manufacturers - November 2015

    International Nuclear Information System (INIS)

    2014-10-01

    CT is the most important source of exposures to radiation in most developed countries today. For this reason CT dose optimisation is of great importance. In this position paper four main stakeholders who are involved in CT dose optimisation are identified. These are the CT manufacturers, the medical doctors, the CT technologists and the medical physicists. HERCA has been working together with the CT manufacturers and COCIR since 2010 following a self-commitment provided by COCIR in 2011. A number of dose optimisation and management tools have been developed by the CT manufacturers and are now available on modern CT scanners. These are presented in this paper. The process of CT dose optimisation can only be achieved if all the stakeholders involved work together as a team and are educated and trained in the use of CT dose optimisation and management tools. The CT manufacturers have an important role in this process. They need to ensure that their staff is properly trained, they need to provide proper education and training to the other three stakeholders involved and these three stakeholders need to find the time and be willing to be trained. This is clearly stated in this position paper with the aim of ensuring appropriate and effective use of CT imaging equipment. On 1 April 2015, HERCA organised a multi-stakeholder meeting kindly hosted by the French Nuclear Safety Authority (ASN) in its premises in Paris. The stakeholders included: - COCIR, supported by the main manufacturers of CT equipment (GE, Philips, Siemens and Toshiba), - The professional organisations: ESR, ESPR, EFRS, EANM, ESTRO and EFOMP, - The international organisations IAEA, EC, and the US FDA (present as observers). The objective of the meeting was to exchange views with a variety of key stakeholders on issues with regard to the optimised use of computed tomography (CT) scanners. The ultimate goal of this focus on dose optimisation is to ensure the best patient care by providing an optimised

  19. [Equipment and technology in robotics].

    Science.gov (United States)

    Murphy, Declan; Challacombe, Ben; Nedas, Tim; Elhage, Oussama; Althoefer, Kaspar; Seneviratne, Lakmal; Dasgupta, Prokar

    2007-05-01

    We review the evolution and current status of robotic equipment and technology in urology. We also describe future developments in the key areas of virtual reality simulation, mechatronics and nanorobotics. The history of robotic technology is reviewed and put into the context of current systems. Experts in the associated fields of nanorobotics, mechatronics and virtual reality simulation simulation review the important future developments in these areas.

  20. Remote handling equipment for SNS

    International Nuclear Information System (INIS)

    Poulten, B.H.

    1983-01-01

    This report gives information on the areas of the SNS, facility which become highly radioactive preventing hands-on maintenance. Levels of activity are sufficiently high in the Target Station Area of the SNS, especially under fault conditions, to warrant reactor technology to be used in the design of the water, drainage and ventilation systems. These problems, together with the type of remote handling equipment required in the SNS, are discussed

  1. Margins related to equipment design

    International Nuclear Information System (INIS)

    Devos, J.

    1994-01-01

    Safety margins related to design of reactor equipment are defined according to safety regulations. Advanced best estimate methods are proposed including some examples which were computed and compared to experimental results. Best estimate methods require greater computation effort and more material data but give better variable accuracy and need careful experimental validation. Simplified methods compared to the previous are less sensitive to material data, sometimes are more accurate but very long to elaborate

  2. Temperature radiation measuring equipment. Temperaturstrahlungsmessgeraet

    Energy Technology Data Exchange (ETDEWEB)

    Lotzer, W

    1981-01-22

    The invention is concerned with a temperature radiation measuring equipment for non-contact temperature measurement by the light intensity variation method, with a photoelectric resistance as the measuring element. By having a circuit with a transistor, the 'dark resistance' occurring in the course of time is compensated for and thus gives a genuine reading (ie. the voltage drop across the photoelectric resistance remains constant).

  3. CERN computing equipment for Senegal

    CERN Multimedia

    Anaïs Schaeffer

    2014-01-01

    On 26 May, CERN once again had the honour of donating computing equipment to a foreign institute.   This time, around 100 servers and five network hubs were sent to Senegal, making it the seventh country, after Morocco, Ghana, Bulgaria, Serbia, Egypt and the Philippines, to receive a donation of computing equipment from the Organization. The official ceremony was held at CERN on 26 May in the presence of the Director-General, Rolf Heuer, and Senegal's ambassador to Geneva, Fodé Seck, who both expressed their enthusiasm for the project. The equipment is intended for Cheikh Anta Diop University (UCAD) in Dakar and will be of particular use to students attending the African School of Fundamental Physics and its Applications (ASP 2014) taking place from 3 to 23 August, for which CERN is a partner. The ASP allows a large number of African students to hone their skills in high-energy physics and to forge professional links with fellow physicists in Africa and Europe. ...

  4. Tank monitor and control system (TMACS) revision 11 acceptance test procedure

    International Nuclear Information System (INIS)

    HOLM, M.J.

    1999-01-01

    The purpose of this document is to describe tests performed to validate Revision 11 of the Tank Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

  5. JCE Online: Equipment Buyers Guide

    Science.gov (United States)

    Holmes, Jon L.

    1999-01-01

    The Equipment Buyers Guide was edited by Jo Rita Jordan. The new Equipment Buyers Guide, bound into the back of this issue, is also a new resource of JCE Internet. This resource provides an online source for the information contained in the printed guide. Placing this information online allows us to regularly update it and to provide live links to the suppliers' WWW sites. The organization of the online version parallels that of the print version. There is an alphabetical list of suppliers and a categorical listing. Links to these lists are provided on every page in the left-hand navigation bar. To quickly find information about a particular supplier, you click Supplier List, click the letter that begins the supplier's name, and scroll through the list to find the supplier. To find which suppliers provide a particular type of instrument or equipment, use the Categories link; click the category of the equipment you are looking for and then click the link to a supplier. You will then be taken to an alphabetical supplier listing page where you can scroll until you find the particular supplier of the item for which you are looking. Once you have found a supplier, the online Equipment Buyers Guide gives you the traditional contact information. But in addition, you also get one-click access to the WWW sites of the suppliers that have them. Depending on the site, you should be able to find information about the items that you seek and may even be able to order the items online! We think that you will find the online version of the Equipment Buyers Guide useful. To make it more useful, please send your suggestions, any errors or omissions you find, and any additional categories to the editor at jjordan@world.std.com The online Equipment Buyers Guide can be found at JCE Online at http://JChemEd.chem.wisc.edu/JCEWWW/Resources/EBG/ JCE Online in '99 JCE Online is your online source of "all things JCE". In order to provide you with an even more useful online resource, JCE

  6. Division of Scientific Equipment - Overview

    International Nuclear Information System (INIS)

    Halik, J.

    2002-01-01

    Full text: The Scientific Equipment Division consists of the Design Group and the Mechanical Workshop. The activity of the Division includes the following: * designs of devices and equipment for experiments in physics; their mechanical construction and assembly. In particular, these are vacuum chambers and installations for HV and UHV;* maintenance and upgrading of the existing installations and equipment in our Institute; * participation of our engineers and technicians in design works, equipment assembly and maintenance for experiments in foreign laboratories. The Design Group is equipped with PC-computers and AutoCAD graphic software (release 2000 and Mechanical Desktop 4.0) and an A0 plotter, which allow us to make drawings and 2- and 3-dimensional mechanical documentation to the world standards. The Mechanical Workshop offers a wide range of machining and treatment methods with satisfactory tolerances and surface quality. They include: * turning - cylindrical elements of a length up to 2000 mm and a diameter up to 400 mm, and also disc type elements of a diameter up to 600 mm and a length not exceeding 300 mm, * milling - elements of length up to 1000 mm and gear wheels of diameter up to 300 mm, * grinding - flat surfaces of dimensions up to 300 mm x 1000 mm and cylindrical elements of a diameter up to 200 mm and a length up to 800 mm, * drilling - holes of a diameter up to 50 mm, * welding - electrical and gas welding, including TIG vacuum-tight welding, * soft and hard soldering, * mechanical works including precision engineering, * plastics treatment - machining and polishing using diamond milling, modelling, lamination of various shapes and materials, including plexiglas, scintillators and light-guides, * painting - paint spraying with possibility of using furnace-fired drier of internal dimensions of 800 mm x 800 mm x 800 mm. Our workshop is equipped with the CNC milling machine which can be used for machining of work pieces up to 500 kg. The machine

  7. CAMAC - A modular instrumentation system for data handling. Revised description and specification

    International Nuclear Information System (INIS)

    1977-03-01

    CAMAC is a modern data handling system in widespread use with on-line digital computers. It is based on a digital highway for data and control. The CAMAC specifications ensures compatibility between equipment from different sources. The revised specification introduces several new features, but is consistent with the previous version (EUR 4100e, 1969). The CAMAC system was specified by European laboratories, through the Esone Committee, and has been endorsed by the USAEC NIM Committee, who have an identical specification (TID-25875)

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

    Energy Technology Data Exchange (ETDEWEB)

    Downey, N.J.

    1994-12-14

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

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

    International Nuclear Information System (INIS)

    Downey, N.J.

    1994-01-01

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

  10. Re-visions of rationality?

    Science.gov (United States)

    Newell, Ben R

    2005-01-01

    The appeal of simple algorithms that take account of both the constraints of human cognitive capacity and the structure of environments has been an enduring theme in cognitive science. A novel version of such a boundedly rational perspective views the mind as containing an 'adaptive toolbox' of specialized cognitive heuristics suited to different problems. Although intuitively appealing, when this version was proposed, empirical evidence for the use of such heuristics was scant. I argue that in the light of empirical studies carried out since then, it is time this 'vision of rationality' was revised. An alternative view based on integrative models rather than collections of heuristics is proposed.

  11. Revised hypothesis and future perspectives

    DEFF Research Database (Denmark)

    Norsk, P; Drummer, C; Christensen, N J

    2001-01-01

    Results from space have been unexpected and not predictable from the results of ground-based simulations. Therefore, the concept of how weightlessness and gravity modulates the regulation of body fluids must be revised and a new simulation model developed. The main questions to ask in the future...... are the following: Does weightlessness induce a diuresis and natriuresis during the initial hours of space flight leading to an extracellular and intravascular fluid volume deficit? Can sodium in excess be stored in a hitherto unknown way, particularly during space flight? Why are fluid and sodium retaining systems...

  12. Used energy-related laboratory equipment grant program for institutions of higher learning. Eligible equipment catalog

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This is a listing of energy related equipment available through the Energy-Related Laboratory Equipment Grant Program which grants used equipment to institutions of higher education for energy-related research. Information included is an overview of the program, how to apply for a grant of equipment, eligibility requirements, types of equipment available, and the costs for the institution.

  13. Data center equipment location and monitoring system

    DEFF Research Database (Denmark)

    2011-01-01

    A data center equipment location system includes both hardware and software to provide for location, monitoring, security and identification of servers and other equipment in equipment racks. The system provides a wired alternative to the wireless RFID tag system by using electronic ID tags...... connected to each piece of equipment, each electronic ID tag connected directly by wires to a equipment rack controller on the equipment rack. The equipment rack controllers then link over a local area network to a central control computer. The central control computer provides an operator interface......, and runs a software application program that communicates with the equipment rack controllers. The software application program of the central control computer stores IDs of the equipment rack controllers and each of its connected electronic ID tags in a database.; The software application program...

  14. A taxonomic revision of the genus Podocarpus

    OpenAIRE

    Laubenfels, de, D.J.

    1985-01-01

    In connection with the forthcoming revision of the Coniferae for the Flora Malesiana, the author thought it necessary to revise the genus Podocarpus. Although this genus has a substantial representation in Malesia (30 species), the revision is too involved to be appropriate with the Flora Malesiana per se. One new subgenus and 17 new sections are described, and 94 species are enumerated, of which 11 species and 1 variety are described as new, and 3 varieties have been raised to specific rank....

  15. Revision Total Hip Arthoplasty: Factors Associated with Re-Revision Surgery

    OpenAIRE

    Khatod, M; Cafri, G; Inacio, MCS; Schepps, AL; Paxton, EW; Bini, SA

    2015-01-01

    The survivorship of implants after revision total hip arthroplasty and risk factors associated with re-revision are not well defined. We evaluated the re-revision rate with use of the institutional total joint replacement registry. The purpose of this study was to determine patient, implant, and surgeon factors associated with re-revision total hip arthroplasty.A retrospective cohort study was conducted. The total joint replacement registry was used to identify patients who had undergone revi...

  16. Revised nonstochastic health effects models

    International Nuclear Information System (INIS)

    Yaniv, S.S.; Scott, B.R.

    1991-01-01

    In 1989, the U.S. Nuclear Regulatory Commission (NRC) published a revision of the 1985 report, Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, NUREG/CR-4214, that included models for early occurring and continuing nonstochastic effects, cancers and thyroid nodules, and genetic effects. This paper discusses specific models for lethality from early occurring and continuing effects. For brevity, hematopoietic-syndrome lethality is called hematopoietic death; pulmonary-syndrome lethality is called pulmonary death; and gastrointestinal syndrome lethality is called gastrointestinal death. Two-parameter Weibull risk functions are recommended for estimating the risk of hematopoietic, pulmonary, or gastrointestinal death. The risks are obtained indirectly by using hazard functions; as a result, this type of approach has been called hazard-function modeling and the models generated are called hazard-function models. In the 1989 NUREG/CR-4214 report, changes were made in the parameter values for a number of effects, and the models used to estimate hematopoietic and pulmonary deaths were substantially revised. Upper and lower estimates of model parameters are provided for all early health effects models. In this paper, we discuss the 1989 models for hematopoietic and pulmonary deaths, highlighting the differences between the 1989 and 1985 models. In addition, we give the reasons for which the 1985 models were modified

  17. Establishment for Nuclear Equipment: Overview

    International Nuclear Information System (INIS)

    Pracz, J.

    2001-01-01

    Full text: The activity of ZdAJ in 2000 was focused on realisation of the Government-Ordered Project - 6/15 MeV Accelerator. The realisation was accomplished in two stages: - stage I should result in deriving principal operational parameters of the accelerator - stage 2 will result in full implementation of the control system providing optimum control of the equipment and automatic maintaining of its parameters. Within the frames of the first stage, a klystron modulator panel was finished and the design documentation of the mechanical supporting structure, the arm, accelerating structure, collimator and control panel were advanced. Manufacturing of the above sub-units in the workshop has started. In the frames of the Specific Project of the State Committee for Scientific Research, the improvement of Neptun lOPC accelerator was undertaken. The read-out of the monitor dose with atmospheric pressure and ambient temperature compensation has been introduced. New filters for equalising the photon and electron beam and new wedge filters have been designed. Changes in programming have been introduced, which improve the patient's safety by eliminating possible personnel errors and increase the accuracy of radiation fields read-out. In 2000 ZdAJ progressed in development of the Quality System conforming EN-ISO 9001 Standard by including the provisions of EN 46001 Standard. The Standard EN 46001: ''Quality Systems - Medical Equipment''. Detailed requirements related to application of EN ISO 9001 is an European Quality Standard extending the provisions of EN ISO 9001 Standard over the manufacturers of medical equipment. (author)

  18. Revising Lecture Notes: How Revision, Pauses, and Partners Affect Note Taking and Achievement

    Science.gov (United States)

    Luo, Linlin; Kiewra, Kenneth A.; Samuelson, Lydia

    2016-01-01

    Note taking has been categorized as a two-stage process: the recording of notes and the review of notes. We contend that note taking might best involve a three-stage process where the missing stage is revision. This study investigated the benefits of revising lecture notes and addressed two questions: First, is revision more effective than…

  19. Reactor vital equipment determination techniques

    International Nuclear Information System (INIS)

    Bott, T.F.; Thomas, W.S.

    1983-01-01

    The Reactor Vital Equipment Determination Techniques program at the Los Alamos National Laboratory is discussed. The purpose of the program is to provide the Nuclear Regulatory Commission (NRC) with technical support in identifying vital areas at nuclear power plants using a fault-tree technique. A reexamination of some system modeling assumptions is being performed for the Vital Area Analysis Program. A short description of the vital area analysis and supporting research on modeling assumptions is presented. Perceptions of program modifications based on the research are outlined, and the status of high-priority research topics is discussed

  20. The replace repair decision for heavy equipment.

    Science.gov (United States)

    2004-01-01

    The fleet of equipment operated by the Virginia Department of Transportation (VDOT) constitutes a large investment, on the order of half a billion dollars. A means of identifying earlier and more accurately those pieces of equipment whose timely repl...

  1. Proceedings of FED remote maintenance equipment workshop

    International Nuclear Information System (INIS)

    Sager, P.; Garin, J.; Hager, E.R.; Spampinato, P.T.; Tobias, D.; Young, N.

    1981-11-01

    A workshop was convened in two sessions in January and March 1981, on the remote maintenance equipment for the Fusion Engineering Device (FED). The objectives of the first session were to familiarize the participants with the status of the design of the FED and to develop a remote maintenance equipment list for the FED. The objective of the second session was to have the participants present design concepts for the equipment which had been identified in the first session. The equipment list was developed for general purpose and special purpose equipment. The general purpose equipment was categorized as manipulators and other, while the special purpose equipment was subdivided according to the reactor subsystem it serviced: electrical, magnetic, and nuclear. Both mobile and fixed base manipulators were identified. Handling machines were identified as the major requirement for special purpose equipment

  2. Musical Sound, Instruments, and Equipment

    Science.gov (United States)

    Photinos, Panos

    2017-12-01

    'Musical Sound, Instruments, and Equipment' offers a basic understanding of sound, musical instruments and music equipment, geared towards a general audience and non-science majors. The book begins with an introduction of the fundamental properties of sound waves, and the perception of the characteristics of sound. The relation between intensity and loudness, and the relation between frequency and pitch are discussed. The basics of propagation of sound waves, and the interaction of sound waves with objects and structures of various sizes are introduced. Standing waves, harmonics and resonance are explained in simple terms, using graphics that provide a visual understanding. The development is focused on musical instruments and acoustics. The construction of musical scales and the frequency relations are reviewed and applied in the description of musical instruments. The frequency spectrum of selected instruments is explored using freely available sound analysis software. Sound amplification and sound recording, including analog and digital approaches, are discussed in two separate chapters. The book concludes with a chapter on acoustics, the physical factors that affect the quality of the music experience, and practical ways to improve the acoustics at home or small recording studios. A brief technical section is provided at the end of each chapter, where the interested reader can find the relevant physics and sample calculations. These quantitative sections can be skipped without affecting the comprehension of the basic material. Questions are provided to test the reader's understanding of the material. Answers are given in the appendix.

  3. Concerning equipment procurement for NPPs

    International Nuclear Information System (INIS)

    Pana, N.

    2002-01-01

    After a stagnation in investments for nuclear power which extended over a period of 10-15 years, assessments done by energy forecast institutes, as well as, evaluations by UE institutions, OECD, and DOE (USA) point to the conclusion solid and argued that the electric energy of nuclear origin will record a new boost beginning probably with the year 2005. Particular efforts were concentrated upon improving the performances of existing plants and, on the other hand, towards new, evolutionary concepts in nuclear engineering. Advanced equipment for nuclear reactors and plants resulted and were already implemented. In Europe construction of both advanced PWR and BWR type reactors are underway. The paper consider the issues of Romanian nuclear power and presents the prospects for advanced CANDU reactors in connection with the Romania's infrastructure and necessities. The problem of modernizing the equipment and components for NPP is discussed in the context of financing and investment conditions. In conclusion, the share of nuclear power in Romania is expected to rise in order to compensate the decline in fossil fuel thermal power and to better solve the environmental issues

  4. Meeting the latest qualification requirements for Class 1E protection system equipment: a practical approach

    International Nuclear Information System (INIS)

    Daigle, R.P.; Breen, R.J.

    1977-01-01

    The requirements for qualifying Class 1E equipment for Nuclear Power Generating Stations were significantly revised in 1974 and 1975. These new requirements reflect the desire of the industry to provide improved methods of determining the qualification of this vital equipment. The revised standards do, in fact, meet these industry goals in a generally acceptable manner. The Nuclear Regulatory Commission is presently requiring utilities to comply with these revised standards and regulatory guides in order to obtain the necessary permits. Manufacturers are developing and implementing programs to comply with the new requirements. One of the more difficult new requirements of qualification is aging to achieve advanced life condition. The objectives and methods described for aging are difficult for much of the equipment within the Protection System. The use of thermal and vibrational techniques to simulate aging is valid for some components (i.e., capacitors, transistors, cable and/or motor insulation) but may be neither valid nor practical for many items (e.g., complete instrument systems, etc.). A seemingly obvious approach, although rarely followed, in regarding new or revised standards is to refrain from making any type of commitment until the standards are thoroughly understood. Often too hasty a decision is made by a utility (concerned about licensing) or a manufacturer (concerned about being competitive) to commit to new requirements. Consequently, the broad range of interpretations that usually develops for a given set of requirements may result in difficult relations between organizations. This paper deals with solutions for qualification in a practical sense, with emphasis on the aging issue and does not elaborate on seismic qualification

  5. Coeficiente de corrección en engranajes cilíndricos como factor de conversión entre sistemas AGMA e ISO. // Addendum modification coefficient as conversion factor of cylindrical gears in AGMA system to ISO standards.

    Directory of Open Access Journals (Sweden)

    G. González Rey

    2007-09-01

    Full Text Available A partir de la experiencia de los autores, en trabajos asociados con el análisis para la reconversión de engranajes ensistemas AGMA a partir de herramientas con referencia a normas ISO, en el artículo se pretende exponer las principalesdefiniciones y recomendaciones asociadas al coeficiente de corrección relativo al módulo en engranajes cilíndricos de ejesparalelos con dientes de flanco de evolvente que permitan un racional cálculo de la geometría del engranaje y apreciarmediante ejemplos la ventaja del coeficiente de corrección en la solución de problemas prácticos de conversión deengranajes en sistemas AGMA a ISO.Palabras claves: geometría de engranaje cilíndrico, coeficiente de corrección, conversión AGMA a ISO________________________________________________________________________________AbstractDefinitions and recommendations associated to the addendum modification coefficient are presented. Examples, based onauthor’s experiences in the analysis, recovery and conversion of helical and spur gears in AGMA system to ISO standards showthe advantage of application of the addendum modification coefficient in the solution of practical problems and rationalcalculation of gears.Key words: external parallel-axis cylindrical involute gears, gear geometry, , ISO gear standards, rack shift coefficient x

  6. Sequenced Peer Revision: Creating Competence and Community

    Science.gov (United States)

    Bowman, Ingrid K.; Robertson, John

    2013-01-01

    Mastering techniques of self- and peer revision is a valuable tool for all writers, especially US-educated Generation 1.5 students, whose near fluency enables them to dialogue successfully about their writing. Using action research, 2 academic writing instructors systematically trained students to more responsibly and effectively revise their…

  7. Equipment available for automating rig operations

    International Nuclear Information System (INIS)

    McNair, W.L.

    1990-01-01

    Several manufacturers are producing automated rig equipment, from complete systems to individual functions for existing drilling rigs. Significant improvements in well site time, costs of operations, and improved drilling performance have led drilling contractors to install this equipment on their rigs. This paper details some of the equipment available for automating rigs

  8. 13 CFR 143.32 - Equipment.

    Science.gov (United States)

    2010-01-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Equipment. 143.32 Section 143.32...

  9. 32 CFR 33.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 32 National Defense 1 2010-07-01 2010-07-01 false Equipment. 33.32 Section 33.32 National Defense...

  10. 45 CFR 92.32 - Equipment.

    Science.gov (United States)

    2010-10-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 45 Public Welfare 1 2010-10-01 2010-10-01 false Equipment. 92.32 Section 92.32 Public Welfare...

  11. 40 CFR 31.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Equipment. 31.32 Section 31.32...

  12. 14 CFR 1273.32 - Equipment.

    Science.gov (United States)

    2010-01-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Equipment. 1273.32 Section 1273.32...

  13. 29 CFR 1470.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 29 Labor 4 2010-07-01 2010-07-01 false Equipment. 1470.32 Section 1470.32 Labor Regulations...

  14. 15 CFR 24.32 - Equipment.

    Science.gov (United States)

    2010-01-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Equipment. 24.32 Section 24.32...

  15. 38 CFR 43.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 38 Pensions, Bonuses, and Veterans' Relief 2 2010-07-01 2010-07-01 false Equipment. 43.32 Section...

  16. 30 CFR 250.602 - Equipment movement.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Equipment movement. 250.602 Section 250.602... OPERATIONS IN THE OUTER CONTINENTAL SHELF Oil and Gas Well-Workover Operations § 250.602 Equipment movement. The movement of well-workover rigs and related equipment on and off a platform or from well to well on...

  17. 30 CFR 250.502 - Equipment movement.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Equipment movement. 250.502 Section 250.502... OPERATIONS IN THE OUTER CONTINENTAL SHELF Oil and Gas Well-Completion Operations § 250.502 Equipment movement. The movement of well-completion rigs and related equipment on and off a platform or from well to well...

  18. 46 CFR 121.220 - Cooking equipment.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Cooking equipment. 121.220 Section 121.220 Shipping... SYSTEMS AND EQUIPMENT Cooking and Heating § 121.220 Cooking equipment. (a) Doors on a cooking appliance... cooking appliance must be installed to prevent movement in heavy seas. (c) For a grill or similar type of...

  19. 46 CFR 184.220 - Cooking equipment.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Cooking equipment. 184.220 Section 184.220 Shipping...) VESSEL CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Cooking and Heating § 184.220 Cooking equipment. (a) Doors on a cooking appliance must be provided with hinges and locking devices to prevent...

  20. Special equipment for etching nitrocellulose film

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1983-08-01

    Nitrocellulose film and converter screens used for neutron radiography are described. Difficulties in visualization of radiographs on those films are mentioned. Because there is no equipment for etching nitrocellulose film available on the market Risoe has designed and produced such equipment at an estimated cost of Dkr. 15,000. Design criteria for this equipment are given and its performance described

  1. Developing equipment for AGR remote visual inspection

    International Nuclear Information System (INIS)

    James, P.W.; Walton, P.J.

    1985-01-01

    The Remote Inspection Group is part of the CEGB's Generation Development and Construction Division, and has responsibility for the design, development, procurement, testing and setting to work of the equipment provided to carry out routine remote visual inspections of its AGRs. This equipment includes both the viewing devices and the necessary placement equipment. (author)

  2. 46 CFR 121.210 - Heating equipment.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Heating equipment. 121.210 Section 121.210 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS CARRYING MORE THAN 150... SYSTEMS AND EQUIPMENT Cooking and Heating § 121.210 Heating equipment. (a) Each heater must be so...

  3. 46 CFR 184.210 - Heating equipment.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Heating equipment. 184.210 Section 184.210 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) VESSEL CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Cooking and Heating § 184.210 Heating equipment...

  4. Sample-related peripheral equipment at IPNS

    International Nuclear Information System (INIS)

    Bohringer, D.E.; Crawford, R.K.

    1985-01-01

    This paper describes samples environment equipment provided by IPNS to visiting users and staff scientists. Of the twelve horizontal neutron beam stations, (ten now operational, two under construction) all use one or more form of such support equipment. An in-house support group devotes a significant fraction of its time to development, calibration, and maintenance of this equipment

  5. 14 CFR 121.605 - Airplane equipment.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Airplane equipment. 121.605 Section 121.605..., FLAG, AND SUPPLEMENTAL OPERATIONS Dispatching and Flight Release Rules § 121.605 Airplane equipment. No person may dispatch or release an airplane unless it is airworthy and is equipped as prescribed in § 121...

  6. Fire prevention and protection for trackless equipment

    Energy Technology Data Exchange (ETDEWEB)

    Burger, A.J.

    1988-10-01

    With the increased use of trackless diesel and electrical equipment underground, the fire danger associated with this equipment has increased. The need for adequate fire prevention and protection on all aspects of trackless mechanised mining must be taken into consideration. This paper describes briefly the causes of fires on trackless equipment and the precautions taken to reduce the risk of ignition. 1 tab.

  7. Load Bearing Equipment for Bone and Muscle

    Science.gov (United States)

    Shackelford, Linda; Griffith, Bryan

    2015-01-01

    Resistance exercise on ISS has proven effective in maintaining bone mineral density and muscle mass. Exploration missions require exercise with similar high loads using equipment with less mass and volume and greater safety and reliability than resistance exercise equipment used on ISS (iRED, ARED, FWED). Load Bearing Equipment (LBE) uses each exercising person to create and control the load to the partner.

  8. Notice to exporters on products prohibited from export (nuclear material, equipment and large nuclear units)

    International Nuclear Information System (INIS)

    1988-01-01

    In order to ensure that the policy to avoid the proliferation of nuclear weapons is complied with, the French Administration applies stricter controls over the export of certain sensitive products, materials and equipment. To this effect, lists of such products, materials and equipment are published in the form of Notices to exporters and periodically revised. This Notice repeals and replaces the previous Notice published in the Official Gazette of 21 January 1986. Annex I contains the list of materials whose export is subject to nuclear non-proliferation controls. Annex II lists the equipment whose export is subject to the same controls. Annex III includes the list of large nuclear units for which an application for prior approval of export must be submitted to the Administrations concerned. (NEA) [fr

  9. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  10. Radiological control manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kloepping, R.

    1996-05-01

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

  11. Potentialities of Revised Quantum Electrodynamics

    Directory of Open Access Journals (Sweden)

    Lehnert B.

    2013-10-01

    Full Text Available The potentialities of a revised quantum electrodynamic theory (RQED earlier established by the author are reconsidered, also in respect to other fundamental theories such as those by Dirac and Higgs. The RQED theory is characterized by intrinsic linear symmetry breaking due to a nonzero divergence of the electric field strength in the vacuum state, as supported by the Zero Point Energy and the experimentally confirmed Casimir force. It includes the results of electron spin and antimatter by Dirac, as well as the rest mass of elementary particles predicted by Higgs in terms of spontaneous nonlinear symmetry breaking. It will here be put into doubt whether the approach by Higgs is the only theory which becomes necessary for explaining the particle rest masses. In addition, RQED theory leads to new results beyond those being available from the theories by Dirac, Higgs and the Standard Model, such as in applications to leptons and the photon.

  12. Hot sample archiving. Revision 3

    International Nuclear Information System (INIS)

    McVey, C.B.

    1995-01-01

    This Engineering Study revision evaluated the alternatives to provide tank waste characterization analytical samples for a time period as recommended by the Tank Waste Remediation Systems Program. The recommendation of storing 40 ml segment samples for a period of approximately 18 months (6 months past the approval date of the Tank Characterization Report) and then composite the core segment material in 125 ml containers for a period of five years. The study considers storage at 222-S facility. It was determined that the critical storage problem was in the hot cell area. The 40 ml sample container has enough material for approximately 3 times the required amount for a complete laboratory re-analysis. The final result is that 222-S can meet the sample archive storage requirements. During the 100% capture rate the capacity is exceeded in the hot cell area, but quick, inexpensive options are available to meet the requirements

  13. Radiological control manual. Revision 1

    International Nuclear Information System (INIS)

    Kloepping, R.

    1996-05-01

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

  14. TU-G-213-02: IEC Subcommittee 62B (Diagnostic Imaging Equipment): Recent and Active Projects

    International Nuclear Information System (INIS)

    Supanich, M.

    2015-01-01

    The International Electrotechnical Commission (IEC) writes standards that manufacturers of electrical equipment must comply with. Medical electrical equipment, such as medical imaging, radiation therapy, and radiation dosimetry devices, fall under Technical Committee 62. Of particular interest to medical physicists are the standards developed within Subcommittees (SC) 62B, which addresses diagnostic radiological imaging equipment, and 62C, which addresses equipment for radiation therapy, nuclear medicine and dosimetry. For example, a Working Group of SC 62B is responsible for safety and quality assurance standards for CT scanners and a Working Group of SC 62C is responsible for standards that set requirements for dosimetric safety and accuracy of linacs and proton accelerators. IEC standards thus have an impact on every aspect of a medical physicist’s job, including equipment testing, shielding design, room layout, and workflow. Consequently, it is imperative that US medical physicists know about existing standards, as well as have input on those under development or undergoing revision. The structure of the IEC and current standards development work will be described in detail. The presentation will explain how US medical physicists can learn about IEC standards and contribute to their development. Learning Objectives: Learn about the structure of the IEC and the influence that IEC standards have on the design of equipment for radiology and radiation therapy. Learn about the mechanisms by which the US participates in the development and revision of standards. Understand the specific requirements of several standards having direct relevance to diagnostic and radiation therapy physicists

  15. TU-G-213-02: IEC Subcommittee 62B (Diagnostic Imaging Equipment): Recent and Active Projects

    Energy Technology Data Exchange (ETDEWEB)

    Supanich, M. [Rush University Medical Center (United States)

    2015-06-15

    The International Electrotechnical Commission (IEC) writes standards that manufacturers of electrical equipment must comply with. Medical electrical equipment, such as medical imaging, radiation therapy, and radiation dosimetry devices, fall under Technical Committee 62. Of particular interest to medical physicists are the standards developed within Subcommittees (SC) 62B, which addresses diagnostic radiological imaging equipment, and 62C, which addresses equipment for radiation therapy, nuclear medicine and dosimetry. For example, a Working Group of SC 62B is responsible for safety and quality assurance standards for CT scanners and a Working Group of SC 62C is responsible for standards that set requirements for dosimetric safety and accuracy of linacs and proton accelerators. IEC standards thus have an impact on every aspect of a medical physicist’s job, including equipment testing, shielding design, room layout, and workflow. Consequently, it is imperative that US medical physicists know about existing standards, as well as have input on those under development or undergoing revision. The structure of the IEC and current standards development work will be described in detail. The presentation will explain how US medical physicists can learn about IEC standards and contribute to their development. Learning Objectives: Learn about the structure of the IEC and the influence that IEC standards have on the design of equipment for radiology and radiation therapy. Learn about the mechanisms by which the US participates in the development and revision of standards. Understand the specific requirements of several standards having direct relevance to diagnostic and radiation therapy physicists.

  16. ADDENDUM: nutraceuticals for protection and healing of gastrointestinal mucosa. Romano M, Vitaglione P, Sellitto S, D'Argenio G. Curr Med Chem 2012, 19: 109-117.

    Science.gov (United States)

    Romano, Marco

    2014-01-01

    This invited review on the beneficial effects of nutraceuticals in the gastrointestinal tract reports previous work conducted by the authors as well as the work by other researchers in this expanding field. The text of our article on several occasions reports sentences very similar or identical to those which appear in the manuscript from which the information was obtained and this applies to both our own work and some other researchers' work. This was mainly due to the fact that we tried to maintain unchanged the original meaning of what we reported in our review. Also, it was our intention to give full credit to the authors of manuscripts dealing with the gastrointestinal effects of nutraceuticals and in some instances we preferred to quote the original paper rather than the review where this original information was taken from. We realize that a number (8) of manuscripts, source of the information reported in our review, were not included in the reference list (which contains over 100 references) and we deeply apologize for this with the authors of the missing references. In most of the cases this was due to a mistake in the final editing of the manuscript. In some other cases this was because we tried not to exceed the number of references requested. We therefore, by means of this addendum, would like to add to the reference list taken out the articles which were not quoted in the manuscript at the time it was published. Two of the articles deal with the effect of nutraceuticals in the upper gastrointestinal tract. The remaining six deal with the effect of nutraceuticals in the lower gastrointestinal tract.

  17. Addendum to the RCRA Assessment Report for Single-Shell Tank Waste Management Area S-SX at the Hanford Site

    International Nuclear Information System (INIS)

    Chou, C.J.; Johnson, V.G.

    1999-01-01

    The initial Resource Conservation and Recovery Act (RCRA) groundwater quality assessment report for Waste Management Area S-SX (PNNL-11810) was issued in January 1998. The report stated a plan for conducting continued assessment would be developed after addressing Washington State Department of Ecology (Ecology) comments on initial findings in PNNL-11810. Comments from Ecology were received by US Department of Energy, Richland Operations Office (DOE-RL) on September 24, 1998. Shortly thereafter, Ecology and DOE began dispute resolution and related negotiations about tank farm vadose issues. This led to proposed new Tri-Party Agreement milestones covering a RCRA Facility Investigation-Corrective Measures Study (RFI/CMS) of the four single-shell tank farm waste management areas that were in assessment status (Waste Management Areas B-BX-BY, S-SX, T and TX-TY). The RCRA Facility Investigation includes both subsurface (vadose zone and groundwater) and surface (waste handling facilities and grounds) characterization. Many of the Ecology comments on PNNL-11810 are more appropriate for, and in many cases are superseded by, the RFI/CMS at Waste Management Area S-SX. The proposed Tri-Party Agreement milestone changes that specify the scope and schedule for the RFI/CMS work plans (Tri-Party Agreement change number M-45-98-0) were issued for public comment in February 1999. The Tri-Party Agreement narrative indicates the ongoing groundwater assessments will be integrated with the RFI/CMS work plans. This addendum documents the disposition of the Ecology comments on PNNL-11810 and identifies which comments were more appropriate for the RFI/CMS work plan

  18. Addendum to the RCRA Assessment Report for Single-Shell Tank Waste Management Area S-SX at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Chou, C.J.; Johnson, V.G.

    1999-10-07

    The initial Resource Conservation and Recovery Act (RCRA) groundwater quality assessment report for Waste Management Area S-SX (PNNL-11810) was issued in January 1998. The report stated a plan for conducting continued assessment would be developed after addressing Washington State Department of Ecology (Ecology) comments on initial findings in PNNL-11810. Comments from Ecology were received by US Department of Energy, Richland Operations Office (DOE-RL) on September 24, 1998. Shortly thereafter, Ecology and DOE began dispute resolution and related negotiations about tank farm vadose issues. This led to proposed new Tri-Party Agreement milestones covering a RCRA Facility Investigation-Corrective Measures Study (RFI/CMS) of the four single-shell tank farm waste management areas that were in assessment status (Waste Management Areas B-BX-BY, S-SX, T and TX-TY). The RCRA Facility Investigation includes both subsurface (vadose zone and groundwater) and surface (waste handling facilities and grounds) characterization. Many of the Ecology comments on PNNL-11810 are more appropriate for, and in many cases are superseded by, the RFI/CMS at Waste Management Area S-SX. The proposed Tri-Party Agreement milestone changes that specify the scope and schedule for the RFI/CMS work plans (Tri-Party Agreement change number M-45-98-0) were issued for public comment in February 1999. The Tri-Party Agreement narrative indicates the ongoing groundwater assessments will be integrated with the RFI/CMS work plans. This addendum documents the disposition of the Ecology comments on PNNL-11810 and identifies which comments were more appropriate for the RFI/CMS work plan.

  19. Establishment for Nuclear Equipment -Overview

    International Nuclear Information System (INIS)

    Pracz, J.

    2006-01-01

    Research and development works conducted in the Establishment for Nuclear Equipment (ZdAJ) were focused around 3 subject areas: an accelerator for cancer treatment, therapeutical tables, systems and methods for controlling objects that cross international borders. The new, medium energy accelerator for cancer therapy cases is being designed in the Establishment for several years. In 2005 progress was achieved. A physical part, containing an electron beam has been completed and the parameters of that beam make it useful for therapeutical purposes. Consequently, the work on designing and testing of beam control systems, ensuring its high stability, repetition of irradiation parameters and accuracy of dosage have been started. Results of these tests make it very probable that 2006 will be the final year of scientific works and in 2007 the new apparatus will be ready for sales. Therapeutical tables have become a leading product of ZdAJ IPJ. Their technical parameters, reliability and universality in uses are appreciated by many customers of ZdAJ. In 2005, the table Polkam 16 was registered by the national Office for Registration of Medical Equipment as the first product of ZdAJ that meets all technical and formal requirements of the safety mark CE. This allows sales of the product on the market of the European Union. The research and development part of designing a therapeutical table for uses in the total body irradiation technique was also concluded in 2005. After the September 11 terrorist attacks on WTC a matter of controlling international borders have become a priority for many countries. In 2005 in ZdAJ IPJ, we conducted many preliminary calculations and experiments analyzing systems of irradiation sources, both photon and neutron as well as systems of detection and designing of signals triggered by controlling objects crossing the border. The results so far have enabled us to formulate a research project which has been positively evaluated by experts and found

  20. Standardization and improvement of safety for radioisotope equipped instruments

    International Nuclear Information System (INIS)

    Sumi, Tetsuo

    1980-01-01

    The safety for radioisotope-equipped instruments is considered. The one is the safety for the source assembly. The radioisotopes employed for radioisotope-equipped instruments are sealed sources which are used in the state of being contained in the enclosures. Many of the enclosures are provided with shutter mechanism for the purpose of emitting radiation only during the period required. If the possible troubles that might lead to the accidents are sampled out of the results of field operation of radiation instruments, and the safety measures for source enclosures are considered in connection with these troubles, it is no exaggeration to say that the safety for source enclosures has been maintained by preventing the critical accidents by the management of users and the cooperation of manufactures though there were the chance for investigating the safety in the common field and the establishment of JIS Z 4614 standard. Another consideration is concerned with the measures to improve the safety. No accident in the past never guarantees no accident in the future. Accumulation of experience is most effective for those measures, and the more experiences the better. It may be most effective that the manufacturers disclose their experiences each other from the wide outlook overcoming the barrier of trade secret. Fortunately, such consciousness has risen since a few years ago, and the investigation group is doing the works in the Japan Radioisotope Association. On the other hand, the reasonable revision of the radiation injury prevention law is desired. (Wakatsuki, Y.)

  1. Communication equipment radiation resistance ensurance

    International Nuclear Information System (INIS)

    Myrova, L.O.; Chelizhenko, A.Z.

    1983-01-01

    A review of works on radiation resistance of electronic equipment (epsilon epsilon) for 15 years is presented. The effect of ionizing radiation appearing as a result of nuclear explosions in nuclear facilities and in outerspace on epsilon epsilon has been considered. Types of radiation effects in epsilon epsilon, radiation effect on semiconductor devices and integrated circUits, types of epsilon epsilon failures, as well as the procass of radiation-resistant epsilon epsilon designing and selection of its main parameters have been described. The methods of epsilon epsilon flowsheet optimization, application of mathematical simulation and peculiarities of ensurance of epsilon epsilon radiation resistance of communication systems are considered. Peculiarities of designing of radiation-resistant quartz generators, secondary power supply sources and amplifiers are discussed

  2. Purex: process and equipment performance

    International Nuclear Information System (INIS)

    Orth, D.A.

    1986-01-01

    The Purex process is the solvent extraction system that uses tributyl phosphate as the extractant for separating uranium and plutonium from irradiated reactor fuels. Since the first flowsheet was proposed at Oak Ridge National Laboratory in 1950, the process has endured for over 30 years with only minor modifications. The spread of the technology was rapid, and worldwide use or research on Purex-type processes was reported by the time of the 1955 Geneva Conference. The overall performance of the process has been so good that there are no serious contenders for replacing it soon. This paper presents: process description; equipment performance (mixer-settlers, pulse columns, rapid contactors); fission product decontamination; solvent effects (solvent degradation products); and partitioning of uranium and plutonium

  3. Automation of a thermogravimetric equipment

    International Nuclear Information System (INIS)

    Mussio, L.; Castiglioni, J.; Diano, W.

    1987-01-01

    A low cost automation of some instruments by means of simple electronic circuits and a microcomputer Apple IIe. type is discussed. The electronic circuits described are: a) a position detector including phototransistors connected as differential amplifier; b) a current source that, using the error signal of the position detector, changes the current through the coil of an electromagnetic balance to restore its zero position; c) a proportional temperature controller, zero volt switching to drive a furnace to a desired temperature; d) an interface temperature regulator-microcomputer to control the temperature regulator by software; e) a multiplexer for an analog input of a commercial interface. Those circuits are applied in a thermogravimetric equipment used also for vapours adsorption. A program in block diagram form is included and is able to record change of mass, time, furnace temperature and to drive the temperature regulator in order to have the heating rates or the temperature plateaux needed for the experiment. (author) [pt

  4. Establishment for Nuclear Equipment: Overview

    International Nuclear Information System (INIS)

    Pracz, J.

    2000-01-01

    Full text: The main objective of the activity of the Establishment for Nuclear Equipment (ZdAJ) in 1999 was to obtain the ISO 9001 certificate. Work on this problem has been successfully completed. The changes introduced in agreement with requirements of ISO in supervising the construction, manufacturing and servicing eliminate possible deficiencies of our products and will pay in the future. Two new important ventures have been undertaken: design of an accelerator with two photon energies and a reconstruction of simulator directed towards better geometrical parameters. The completion of the improvements in accelerator is foreseen for the year 2002. The changes comprise almost all sub-assemblies of the device. The modernized simulator will be installed in the hospital already in the year 2000 - the ameliorations concern mainly the arm of the apparatus, collimator, driving gears and control system. Of course - apart from this, the routine production activity of the Establishment was continued in 1999. (author)

  5. Protective equipment use among female rugby players.

    Science.gov (United States)

    Comstock, R Dawn; Fields, Sarah K; Knox, Christy L

    2005-07-01

    Our objective was to assess the prevalence of protective equipment use and the motivation for using protective equipment among a sample of US female rugby players. We surveyed a convenience sample of 234 current US female rugby players from 14 teams participating in a US women's rugby tournament, obtaining self-reported demographic, rugby exposure, and protective equipment use information. Mouthguards were the most commonly used piece of protective equipment: 90.8% of players reported having always worn a mouthguard while playing or practicing rugby within their most recent 3 months of play. Fewer than 15% of players reported having always worn other types of protective equipment. Equipment use varied by playing position. Whereas over 80% of players in all other positions always wore a mouthguard, 66.7% of scrum halves reported always wearing one. Both backs and forwards reported wearing shoulder pads, but only forwards reported always wearing padded headgear. Mouthguards, padded headgear, and shoulder pads were worn "to prevent injury," whereas ankle braces, neoprene sleeves, and athletic tape on joints were worn "to protect a current/recent injury." This is the first study of female rugby players to assess the prevalence of protective equipment use by playing position and the motivation for using protective equipment. With the exception of mouthguards, US female rugby players infrequently use protective equipment. Protective equipment use varies by playing position. Some types of protective equipment appear to be used as primary prevention mechanisms, whereas others are used as secondary or tertiary prevention mechanisms.

  6. Changing nature of equipment and parts qualification

    International Nuclear Information System (INIS)

    Bucci, R.M.

    1988-01-01

    Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

  7. Free-world microelectronic manufacturing equipment

    Science.gov (United States)

    Kilby, J. S.; Arnold, W. H.; Booth, W. T.; Cunningham, J. A.; Hutcheson, J. D.; Owen, R. W.; Runyan, W. R.; McKenney, Barbara L.; McGrain, Moira; Taub, Renee G.

    1988-12-01

    Equipment is examined and evaluated for the manufacture of microelectronic integrated circuit devices and sources for that equipment within the Free World. Equipment suitable for the following are examined: single-crystal silicon slice manufacturing and processing; required lithographic processes; wafer processing; device packaging; and test of digital integrated circuits. Availability of the equipment is also discussed, now and in the near future. Very adequate equipment for most stages of the integrated circuit manufacturing process is available from several sources, in different countries, although the best and most widely used versions of most manufacturing equipment are made in the United States or Japan. There is also an active market in used equipment, suitable for manufacture of capable integrated circuits with performance somewhat short of the present state of the art.

  8. 9 CFR 590.502 - Equipment and utensils; PCB-containing equipment.

    Science.gov (United States)

    2010-01-01

    ... Sanitary Standards and accepted practices currently in effect for such equipment. (c) New or replacement equipment or machinery (including any replacement parts) brought onto the premises of any official plant... equipment and machinery, and any replacement parts for such equipment and machinery. Totally enclosed...

  9. The economic impact of revision otologic surgery.

    Science.gov (United States)

    Nadimi, Sahar; Leonetti, John P; Pontikis, George

    2016-03-01

    Revision otologic surgery places a significant economic burden on patients and the healthcare system. We conducted a retrospective chart analysis to estimate the economic impact of revision canal-wall-down (CWD) mastoidectomy. We reviewed the medical records of all 189 adults who had undergone CWD mastoidectomy performed by the senior author between June 2006 and August 2011 at Loyola University Medical Center in Maywood, Ill. Institutional charges and collections for all patients were extrapolated to estimate the overall healthcare cost of revision surgery in Illinois and at the national level. Of the 189 CWD mastoidectomies, 89 were primary and 100 were revision procedures. The total charge for the revision cases was $2,783,700, and the net reimbursement (collections) was $846,289 (30.4%). Using Illinois Hospital Association data, we estimated that reimbursement for 387 revision CWD mastoidectomies that had been performed in fiscal year 2011 was nearly $3.3 million. By extrapolating our data to the national level, we estimated that 9,214 patients underwent revision CWD mastoidectomy in the United States during 2011, which cost the national healthcare system roughly $76 million, not including lost wages and productivity. Known causes of failed CWD mastoidectomies that often result in revision surgery include an inadequate meatoplasty, a facial ridge that is too high, residual diseased air cells, and recurrent cholesteatoma. A better understanding of these factors can reduce the need for revision surgery, which could have a positive impact on the economic strain related to this procedure at the local, state, and national levels.

  10. Cochlear implant revision surgeries in children.

    Science.gov (United States)

    Amaral, Maria Stella Arantes do; Reis, Ana Cláudia Mirândola B; Massuda, Eduardo T; Hyppolito, Miguel Angelo

    2018-02-16

    The surgery during which the cochlear implant internal device is implanted is not entirely free of risks and may produce problems that will require revision surgeries. To verify the indications for cochlear implantation revision surgery for the cochlear implant internal device, its effectiveness and its correlation with certain variables related to language and hearing. A retrospective study of patients under 18 years submitted to cochlear implant Surgery from 2004 to 2015 in a public hospital in Brazil. Data collected were: age at the time of implantation, gender, etiology of the hearing loss, audiological and oral language characteristics of each patient before and after Cochlear Implant surgery and any need for surgical revision and the reason for it. Two hundred and sixty-five surgeries were performed in 236 patients. Eight patients received a bilateral cochlear implant and 10 patients required revision surgery. Thirty-two surgeries were necessary for these 10 children (1 bilateral cochlear implant), of which 21 were revision surgeries. In 2 children, cochlear implant removal was necessary, without reimplantation, one with cochlear malformation due to incomplete partition type I and another due to trauma. With respect to the cause for revision surgery, of the 8 children who were successfully reimplanted, four had cochlear calcification following meningitis, one followed trauma, one exhibited a facial nerve malformation, one experienced a failure of the cochlear implant internal device and one revision surgery was necessary because the electrode was twisted. The incidence of the cochlear implant revision surgery was 4.23%. The period following the revision surgeries revealed an improvement in the subject's hearing and language performance, indicating that these surgeries are valid in most cases. Copyright © 2018 Associação Brasileira de Otorrinolaringologia e Cirurgia Cérvico-Facial. Published by Elsevier Editora Ltda. All rights reserved.

  11. Quality assurance for radiodiagnostic equipment in Uruguay

    International Nuclear Information System (INIS)

    Cotelo, Elena D.

    2001-01-01

    Since Uruguay did not have an study on X-ray equipment, students of Radiation Protection course (RP) made this field work throughout the country. The objective is to obtain information on the number and kind of X-ray radiodiagnostic equipment. Some of the results are: there are 666 radiodiagnostic equipment. The ratio of population to equipment is 4.515 to 1 in the capital and the mean rate in the rest of the country is 4.383 to one, with a minimum of 1.707 and a maximum of 8.220. The Public Health Ministry (MSP) and the Instituciones de Asistencia Medica Colectiva (a kind of private heath assurance) (IAMC) have less equipment in the capital than in the rest of the country. The 37% of the capital population receives assistance through the IAMC , with a 42.5 % of the equipment. Uruguay except the capital has 18 districts and 17 computed tomography equipment, from which only 3 belong to the MSP. Five districts do not have any. In Montevideo, there are 11.500 females over forty years of age per X-ray mammography equipment, and this relation in the rest of the country is 13.900. There are 21 X-ray Interventional radiology equipment, 16 of them are in the capital. Is from relating the radiodiagnostic equipment, the population and the procedures, that quality assistance indicators emerge. This owns high importance on the way to create a RP National Programme. (author)

  12. Revision of infected knee arthroplasties in Denmark

    DEFF Research Database (Denmark)

    Lindberg-Larsen, Martin; Jørgensen, Christoffer C; Bagger, Jens

    2016-01-01

    Background and purpose - The surgical treatment of periprosthetic knee infection is generally either a partial revision procedure (open debridement and exchange of the tibial insert) or a 2-stage exchange arthroplasty procedure. We describe the failure rates of these procedures on a nationwide...... basis. Patients and methods - 105 partial revisions (100 patients) and 215 potential 2-stage revision procedures (205 patients) performed due to infection from July 1, 2011 to June 30, 2013 were identified from the Danish Knee Arthroplasty Register (DKR). Failure was defined as surgically related death...

  13. Maintenance implementation plan for the Plutonium Finishing Plant. Revision 3

    International Nuclear Information System (INIS)

    Meldrom, C.A.

    1996-03-01

    This document outlines the Maintenance Implementation Plan (MIP) for the Plutonium Finishing Plant (PFP) located at the Hanford site at Richland, Washington. This MIP describes the PFP maintenance program relative to DOE order 4330.4B. The MIP defines the key actions needed to meet the guidelines of the Order to produce a cost-effective and efficient maintenance program. A previous report identified the presence of significant quantities of Pu-bearing materials within PFP that pose risks to workers. PFP's current mission is to develop, install and operate processes which will mitigate these risks. The PFP Maintenance strategy is to equip the facility with systems and equipment able to sustain scheduled PFP operations. The current operating run is scheduled to last seven years. Activities following the stabilization operation will involve an Environmental Impact Statement (EIS) to determine future plant activities. This strategy includes long-term maintenance of the facility for safe occupancy and material storage. The PFP maintenance staff used the graded approach to dictate the priorities of the improvement and upgrade actions identified in Chapter 2 of this document. The MIP documents PFP compliance to the DOE 4330.4B Order. Chapter 2 of the MIP follows the format of the Order in addressing the eighteen elements. As this revision is a total rewrite, no sidebars are included to highlight changes

  14. Individual questions of financial control and revision

    Directory of Open Access Journals (Sweden)

    В. М. Глібко

    2015-05-01

    Full Text Available Problem setting. In modern conditions at investigation and gathering of proofs in criminal proceedings according to item 93 CPC of Ukraine collecting of proofs which is carried out by the criminal proceedings parties, victim is important, the representative of the legal person, in which relation carries out manufacture, including a way истребования and receptions from public authorities, local governments, the enterprises, establishments and organisations, official and physical persons of things, documents, data, conclusions of experts, conclusions of revisions and certificates of checks. Recent research and publications analisis. In scientific sources questions of carrying out of revisions S. B.Zhivko, V.V.Akimov, G.Demjanchuk, J.Buzdugan is considered. Paper objective. Article purpose is studying and definition of a place of revision among forms of inspection of the state control and use of results of revision in criminal proceedings. Paper main body. Off-schedule exit revision that is revision which is not provided in plans of work of body of the state financial control is considered and is spent at presence at least one of the circumstances listed in item 11 of the Law of Ukraine «About main principles of realisation of the state financial control in Ukraine». If revision is carried out on request of investigating bodies it is spent on the basis of the petition of the inspector and accepted by the results of consideration of this petition of the decision of the investigatory judge. The primary goal of revision on request of investigating bodies or on the basis of court definition is reception of proofs on business. Therefore the revision certificate admits the written proof as on the basis of its conclusion of the inspector, the public prosecutor receives the information on a perfect crime, abusing, and also on the persons who have committed a crime, on the period of commission of crime and an amount of damage. In criminal

  15. Inspection device for buried equipment

    International Nuclear Information System (INIS)

    Hanawa, Jun.

    1994-01-01

    In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

  16. Equipment used in nuclear medicine

    International Nuclear Information System (INIS)

    Das, B.K.; Noreen Norfaraheen Lee Abdullah

    2012-01-01

    Detection of radiation is the common purpose of all equipment's and instruments used in radioisotope laboratories. The first and most important instrument that was used in nuclear medicine was Geiger tube developed by H.W. Geiger as early in 1908. He in association with Mueller developed the so called Geiger-Muller tube (GM tube) which could be used to detect beta and gamma radiations. In spite of its severe limitations, GM tube remained the only external counting device until 1949. In 1948, Kallman reported that the scintillations can be detected and amplified with the help of photomultiplier tubes (PMTs). In comparison with gas filled detectors, scintillation detectors have two principal advantages that augment their use in nuclear medicine. Firstly, they are capable of much higher counting rates because of fast resolving times and secondly, because they are much more efficient for gamma ray detection. The scintillation detector is the most basic block of any modern radioisotope detection instrument like rate meter, counter, scanner, gamma camera or single photon emission computed tomography. (author)

  17. Ageing management and equipment qualification

    International Nuclear Information System (INIS)

    Stahl, Gunnar

    2014-01-01

    The knowledge of how the environment and load of organic material in general and especially polymers and lubricants, is affecting the degradation of important properties, have increased during the last decade. However the restrictions using established additives like some color pigments due to their poisonousness e.g. pigments based at cadmium, lead, mercury etc. have caused problems when replacing additives to polymers. The replacement additives have often been used in new design without going through the required material qualification procedure. There have also been observed that some non-qualified and non-approved materials have been installed in some power plants due to false documentation. There are also a lot of new manufacturers, of materials similar to the previously qualified materials, active at the market. This increases the difficulty to ensure that the required material quality is used. New materials, new additives and new manufacturers makes if more and more difficult to assure that the expected material is present. This causes more strict demands of how the new materials often used in equipment at type-testing and in replacement materials are analyzed and documented. By implementing new steps for chemical, mechanical and electrical analysis and increase the general quality assurance content this issue can be managed. (authors)

  18. Equipment selection for atmospheric drying

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, P D; Bhattacharyya, S [Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    Heavy water management is a major factor in deciding the economics of the PHWRs. Hence it is necessary to have an efficient recovery system, for the heavy water vapour escaping from various process systems and maintain a dry atmosphere in the recovery areas. While the basic objective of the atmospheric drying system is to maximize recovery and to minimize stack losses, it is equally important to optimally design the system with due consideration to operational and maintenance aspects. At present, heavy water vapour recovery in the existing Nuclear Power Plants (NPPs) is carried out by dryers of dual fixed bed design. While moving bed design could have some advantages, this has not been adopted so far because of the cumbersome mechanical design involved and special requirements for nuclear application. Developmental work done in this direction has resulted in compact alternative designs. In one of the designs, the change over from adsorption to regeneration is achieved by rotating the bed slowly. This concept is further refined in another alternative using a dessicant wheel. This paper contains brief equipment description of different designs; enumerates the design requirements of an atmospheric drying system for reactor building; describes steps for designing fixed bed type D{sub 2}O vapour recovery system, and highlights advances in dryer technology. (author). 2 refs., 4 figs., 1 ill.

  19. Materials division facilities and equipment

    International Nuclear Information System (INIS)

    Biest, O. v.d.

    1984-01-01

    The research activities of the Division at the Petten Establishment have the aims of characterising the properties of high temperature materials in industrial process environments and of understanding the structures involved in order to gain an insight into behavioural mechanisms. Metallic materials fall within the scope of the programme; the activities are, at present, almost entirely concerned with austenitic steels and nickel based alloys. Starting in 1984, advanced ceramic materials will be studied as well. The equipment available permits the study of mechanical properties in controlled gaseous environments, of the rates and mechanisms of corrosive reactions between materials and those environments, and of the surface and bulk structures by advanced physical techniques. Special preparation and treatment techniques are available. The Division has developed a Data Bank on high temperature alloys. It also operates an information Centre, the activities of which include the organisation of scientific meetings, the commissioning of ''state of the art'' studies on topics in the field of high temperature materials and their applications and the development of a inventory of current research activities in the field in Europe. This booklet is intended to present the facilities and services of the Division to the organizations which are interested in its programmes of work

  20. ISS qualified thermal carrier equipment

    Science.gov (United States)

    Deuser, Mark S.; Vellinger, John C.; Jennings, Wm. M.

    2000-01-01

    Biotechnology is undergoing a period of rapid and sustained growth, a trend which is expected to continue as the general population ages and as new medical treatments and products are conceived. As pharmaceutical and biomedical companies continue to search for improved methods of production and, for answers to basic research questions, they will seek out new avenues of research. Space processing on the International Space Station (ISS) offers such an opportunity! Space is rapidly becoming an industrial laboratory for biotechnology research and processing. Space bioprocessing offers exciting possibilities for developing new pharmaceuticals and medical treatments, which can be used to benefit mankind on Earth. It also represents a new economic frontier for the private sector. For over eight years, the thermal carrier development team at SHOT has been working with government and commercial sector scientists who are conducting microgravity experiments that require thermal control. SHOT realized several years ago that the hardware currently being used for microgravity thermal control was becoming obsolete. It is likely that the government, academic, and industrial bioscience community members could utilize SHOT's hardware as a replacement to their current microgravity thermal carrier equipment. Moreover, SHOT is aware of several international scientists interested in utilizing our space qualified thermal carrier. SHOT's economic financing concept could be extremely beneficial to the international participant, while providing a source of geographic return for their particular region. Beginning in 2000, flight qualified thermal carriers are expected to be available to both the private and government sectors. .

  1. Diagnostics of Electric Equipment Windings

    Directory of Open Access Journals (Sweden)

    I. I. Branovitsky

    2007-01-01

    Full Text Available The paper presents methodology and results of the investigations pertaining to study of influence of short-circuited turns on transient electrical processes in electric motor windings. Dependence of their damped speed and value of the difference signal, obtained at reciprocal subtraction of damped oscillation curves in absence and in presence of short-circuited turns, on number of turns in the tested windings. It has been determined that damped oscillation curves, immediately attributed to short-circuited turns, have peak values along temporary axis which are areas of the largest transient process sensitivity to КЗ turns.Methodology for diagnostics of single- and three-phase electric motor windings and also other electric equipment, being realized in DO-1 device, has been developed in the paper. The men­tioned device makes it possible to carry out visual comparison and quantitative analysis of damped oscillation curves in the tested windings with standard ones which are set in the device memory and their difference signals.

  2. WP EMPLACEMENT CONTROL AND COMMUNICATION EQUIPMENT DESCRIPTIONS

    International Nuclear Information System (INIS)

    Raczka, N.T.

    1997-01-01

    The objective and scope of this document are to list and briefly describe the major control and communication equipment necessary for waste package emplacement at the proposed nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the required equipment are explained and summarized in the individual subsections of this document. This task was evaluated in accordance with QAP-2-0 and found not to be quality affecting. Therefore, this document was prepared in accordance with NAP-MG-012. The following control and communication equipment are addressed in this document: (1) Programmable Logic Controllers (PLC's); (2) Leaky Feeder Radio Frequency Communication Equipment; (3) Slotted Microwave guide Communication Equipment; (4) Vision Systems; (5) Radio Control Equipment; and (6) Enclosure Cooling Systems

  3. Procurement strategic analysis of nuclear safety equipment

    International Nuclear Information System (INIS)

    Wu Caixia; Yang Haifeng; Li Xiaoyang; Li Shixin

    2013-01-01

    The nuclear power development plan in China puts forward a challenge on procurement of nuclear safety equipment. Based on the characteristics of the procurement of nuclear safety equipment, requirements are raised for procurement process, including further clarification of equipment technical specification, establishment and improvement of the expert database of the nuclear power industry, adoption of more reasonable evaluation method and establishment of a unified platform for nuclear power plants to procure nuclear safety equipment. This paper makes recommendation of procurement strategy for nuclear power production enterprises from following aspects, making a plan of procurement progress, dividing procurement packages rationally, establishing supplier database through qualification review and implementing classified management, promoting localization process of key equipment continually and further improving the system and mechanism of procurement of nuclear safety equipment. (authors)

  4. Improved servicing equipment for steam generators

    International Nuclear Information System (INIS)

    Hedtke, James C.

    1998-01-01

    To help keep personnel exposure as low as reasonably achievable and reduce critical path outage time, most nuclear plants of PWR design in the USA are now using improved equipment to service their steam generators (SGs) during outages. Because of the success of this equipment in the USA, two Belgian plants and one English plant have purchased this equipment, and other nuclear plants in Europe are also considering procurement. The improved SG servicing equipment discussed in this paper discusses consists of nozzle dams, segmented multi-stud tensioner, primary manway cover handling tool set, shield door and fastener cleaner. This equipment is specifically designed for the individual plant application and can also be specified for replacement SG projects. All of the equipment can be used without modification of the existing SGs. (author)

  5. Equipment Replacement Decision Making: Opportunities and Challenges

    OpenAIRE

    Fan, Wei (David); Gemar, Mason D.; Machemehl, Randy

    2012-01-01

    The primary function of equipment managers is to replace the right equipment at the right time and at the lowest overall cost. In this paper, the opportunities and challenges associated with equipment replacement optimization (ERO) are discussed in detail. First, a comprehensive review of the state-of-the art and state-of-the practice literature for the ERO problem is conducted. Second, a dynamic programming (DP) based optimization solution methodology is presented to solve the ERO problem. T...

  6. History and development of the tennis equipment

    OpenAIRE

    Horáková, Kateřina

    2007-01-01

    Title: History and development of the tennis equipment. Aim of the work: Process an integral, tabular and synoptic historical development overview of the tennis equipment. This owerview will cover the period since the early beginnings of the game to present days. Methods: Advance work has historical charakter therefore used methods are historiogaphical methods such as chronological method and historical method. Results: Produce tabular description of the tennis equipment by means of reading a...

  7. Mine railway equipments management information system

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, X.; Han, K.; Duan, T.; Liu, Z.; Lu, H. [China University of Mining and Technology, Xuzhou (China)

    2007-06-15

    Based on client/server and browser/server models, the management information system described realized the entire life-cycle management of mine railway equipment which included universal equipment and special equipment in the locomotive depot, track maintenance division, electrical depot and car depot. The system has other online functions such as transmitting reports, graphics management, statistics, searches, graphics wizard and web propaganda. It was applied in Pingdingshan Coal Co. Ltd.'s Railway Transport Department. 5 refs., 4 figs.

  8. Taxation and Welfare: A Revision Exercise.

    Science.gov (United States)

    Boden, Andrew

    1992-01-01

    Offers a revision exercise intended to remind students of some economic terminology associated with taxation and welfare. Provides a set of definitions for which students are to supply matching terms. Includes an answer list and suggests related exercises. (SG)

  9. Student-initiated revision in child health.

    Science.gov (United States)

    Alfaham, M; Gray, O P; Davies, D P

    1994-03-01

    Most teaching of child health in Cardiff takes place in block attachments of 8 weeks. There is an introductory seminar of 2 days followed by a 6-week clinical attachment in a district general hospital in Wales, and then a revision period of one week designed to help students formalize and structure their basic knowledge and to clarify aspects of child health which they may have had difficulty in understanding. The revision programme has to take into account: the short time available, the small number of teaching staff, the most relevant basic knowledge and active participation by the student. This paper describes how this week has been improved through the use of student-initiated revision (SIR). The students' appraisal of this revision and in particular SIR is presented.

  10. New and revised standards for coke production

    Energy Technology Data Exchange (ETDEWEB)

    G.A. Kotsyuba; M.I. Alpatov; Y.G. Shapoval [Giprokoks, the State Institute for the Design of Coke-Industry Enterprises, Kharkov (Ukraine)

    2009-07-15

    The need for new and revised standards for coke production in Ukraine and Russia is outlined. Such standards should address improvements in plant operation, working conditions, environmental protection, energy conservation, fire and explosion safety, and economic indices.

  11. FFTF operations procedures preparation guide. Revision 2

    International Nuclear Information System (INIS)

    1976-12-01

    The Guide is intended to provide guidelines for the initial preparation of FFTF Operating Procedures. The Procedures Preparation Guide was developed from the plan presented and approved in the FFTF Reactor Plant Procedures Plan, PC-1, Revision 3

  12. Revising incompletely specified convex probabilistic belief bases

    CSIR Research Space (South Africa)

    Rens, G

    2016-04-01

    Full Text Available revision employing the notion of optimum entropy, and point out some of the benefits and difficulties in those methods. Both the boundary distribution method and the optimum entropy method are reasonable, yet yield different results....

  13. Descriptor revision belief change through direct choice

    CERN Document Server

    Hansson, Sven Ove

    2017-01-01

    This book provides a critical examination of how the choice of what to believe is represented in the standard model of belief change. In particular the use of possible worlds and infinite remainders as objects of choice is critically examined. Descriptors are introduced as a versatile tool for expressing the success conditions of belief change, addressing both local and global descriptor revision. The book presents dynamic descriptors such as Ramsey descriptors that convey how an agent’s beliefs tend to be changed in response to different inputs. It also explores sentential revision and demonstrates how local and global operations of revision by a sentence can be derived as a special case of descriptor revision. Lastly, the book examines revocation, a generalization of contraction in which a specified sentence is removed in a process that may possibly also involve the addition of some new information to the belief set.

  14. DWPF Development Plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Holtzscheiter, E.W.

    1994-05-09

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ``DWPF Process Development Systems.`` To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant.

  15. DWPF Development Plan. Revision 1

    International Nuclear Information System (INIS)

    Holtzscheiter, E.W.

    1994-01-01

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ''DWPF Process Development Systems.'' To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant

  16. Aircraft Wiring Support Equipment Integration Laboratory (AWSEIL)

    Data.gov (United States)

    Federal Laboratory Consortium — Purpose:The Aircraft Wiring Support Equipment Integration Laboratory (AWSEIL) provides a variety of research, design engineering and prototype fabrication services...

  17. Making petroleum equipment safe, a priority

    International Nuclear Information System (INIS)

    1999-01-01

    Changes to the 'Act respecting the use of petroleum products' have been announced effective May 1, 1999. The changes have been made to reduce problems which can be attributed to petroleum product leaks. The new regulations will make owners and users of petroleum equipment, including underground and above-ground storage equipment and commercial storage tanks, more accountable for the use of their own equipment. The emphasis in the new regulations is based upon the storage capacity of petroleum equipment and the risks associated with this equipment, rather than the on the activities of the owners concerned. Accordingly, the new regulations call for stricter requirements for high-risk equipment, a private equipment inspection plan, a two-year operating permit, replacing the current permits and certificates, a tariff structure based on the risks associated with the equipment, and deregulation of commercial activities involving petroleum products that require no equipment. Additionally, the amendments to the Act transfer responsibility for administration to the Regie du batiment and to the Ministere des Transports. Details of each of these changes are explained

  18. Utility equipment systems: promising more for less

    Energy Technology Data Exchange (ETDEWEB)

    1987-10-01

    This paper discusses current developments in utility equipment systems, a term applied to carrier vehicles, mostly evolved from well-known forms of construction or mining equipment modified to work with a variety of different front or back end attachments. One of the equipment ranges discussed is the Normet cassette system produced by the Orion corporation of Finland, which allows a basic chassis to be converted from a personnel carrier to an ANFO carrier within minutes. LHD vehicles which are being adapted to fulfil multipurpose roles, such as carrying roof supports, chocks and other heavy mining equipment underground are also discussed. 5 figs.

  19. Detection of Equipment Faults Before Beam Loss

    CERN Document Server

    Galambos, J.

    2016-01-01

    High-power hadron accelerators have strict limits on fractional beam loss. In principle, once a high-quality beam is set up in an acceptable state, beam loss should remain steady. However, in practice, there are many trips in operational machines, owing to excessive beam loss. This paper deals with monitoring equipment health to identify precursor signals that indicate an issue with equipment that will lead to unacceptable beam loss. To this end, a variety of equipment and beam signal measurements are described. In particular, several operational examples from the Spallation Neutron Source (SNS) of deteriorating equipment functionality leading to beam loss are reported.

  20. 21 CFR 866.4500 - Immunoelectrophoresis equipment.

    Science.gov (United States)

    2010-04-01

    ... (CONTINUED) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents... clinical use with its electrical power supply is a device used for separating protein molecules...

  1. PROMSYS, Plant Equipment Maintenance and Inspection Scheduling

    International Nuclear Information System (INIS)

    Morgan, D.L.; Srite, B.E.

    1986-01-01

    1 - Description of problem or function: PROMSYS is a computer system designed to automate the scheduling of routine maintenance and inspection of plant equipment. This 'programmed maintenance' provides the detailed planning and accomplishment of lubrication, inspection, and similar repetitive maintenance activities which can be scheduled at specified predetermined intervals throughout the year. The equipment items included are the typical pumps, blowers, motors, compressors, automotive equipment, refrigeration units, filtering systems, machine shop equipment, cranes, elevators, motor-generator sets, and electrical switchgear found throughout industry, as well as cell ventilation, shielding, containment, and material handling equipment unique to nuclear research and development facilities. Four related programs are used to produce sorted schedule lists, delinquent work lists, and optional master lists. Five additional programs are used to create and maintain records of all scheduled and unscheduled maintenance history. 2 - Method of solution: Service specifications and frequency are established and stored. The computer program reviews schedules weekly and prints, on schedule cards, instructions for service that is due the following week. The basic output from the computer program comes in two forms: programmed-maintenance schedule cards and programmed-maintenance data sheets. The data sheets can be issued in numerical building, route, and location number sequence as equipment lists, grouped for work assigned to a particular foreman as the foreman's equipment list, or grouped by work charged to a particular work order as the work-order list. Data sheets grouped by equipment classification are called the equipment classification list

  2. Equipment Reliability Process in Krsko NPP

    International Nuclear Information System (INIS)

    Gluhak, M.

    2016-01-01

    To ensure long-term safe and reliable plant operation, equipment operability and availability must also be ensured by setting a group of processes to be established within the nuclear power plant. Equipment reliability process represents the integration and coordination of important equipment reliability activities into one process, which enables equipment performance and condition monitoring, preventive maintenance activities development, implementation and optimization, continuous improvement of the processes and long term planning. The initiative for introducing systematic approach for equipment reliability assuring came from US nuclear industry guided by INPO (Institute of Nuclear Power Operations) and by participation of several US nuclear utilities. As a result of the initiative, first edition of INPO document AP-913, 'Equipment Reliability Process Description' was issued and it became a basic document for implementation of equipment reliability process for the whole nuclear industry. The scope of equipment reliability process in Krsko NPP consists of following programs: equipment criticality classification, preventive maintenance program, corrective action program, system health reports and long-term investment plan. By implementation, supervision and continuous improvement of those programs, guided by more than thirty years of operating experience, Krsko NPP will continue to be on a track of safe and reliable operation until the end of prolonged life time. (author).

  3. NRC revision to 10 CFR Part 20

    International Nuclear Information System (INIS)

    Baker, R.E.; Cool, W.S.; Mills, W.A.

    1983-01-01

    The Nuclear Regulatory Commission's pollution standards have been revised since publication in the late 1950s, but the basic approach has not changed. The revisions resulted in inaccuracies, conflicts, and ambiguities in requirements. The need for comprehensive updating including radiation-protection principles, risk, occupational exposure dose limits, standards for the public (including de minimis level), surveys and monitoring, disposal into sewerage systems, and records is discussed. 2 tables

  4. Revised data taking schedule with ion beams

    CERN Document Server

    Gazdzicki, Marek; Aduszkiewicz, A; Andrieu, B; Anticic, T; Antoniou, N; Argyriades, J; Asryan, A G; Baatar, B; Blondel, A; Blumer, J; Boldizsar, L; Bravar, A; Brzychczyk, J; Bubak, A; Bunyatov, S A; Choi, K U; Christakoglou, P; Chung, P; Cleymans, J; Derkach, D A; Diakonos, F; Dominik, W; Dumarchez, J; Engel, R; Ereditato, A; Feofilov, G A; Fodor, Z; Ferrero, A; Gazdzicki, M; Golubeva, M; Grebieszkow, K; Grzeszczuk, A; Guber, F; Hasegawa, T; Haungs, A; Igolkin, S; Ivanov, A S; Ivashkin, A; Kadija, K; Katrynska, N; Kielczewska, D; Kikola, D; Kisiel, J; Kobayashi, T; Kolesnikov, V I; Kolev, D; Kolevatov, R S; Kondratiev, V P; Kowalski, S; Kurepin, A; Lacey, R; Laszlo, A; Lyubushkin, V V; Majka, Z; I Malakhov, A; Marchionni, A; Marcinek, A; Maris, I; Matveev, V; Melkumov, G L; Meregaglia, A; Messina, M; Mijakowski, P; Mitrovski, M; Montaruli, T; Mrówczynski, St; Murphy, S; Nakadaira, T; Naumenko, P A; Nikolic, V; Nishikawa, K; Palczewski, T; Pálla, G; Panagiotou, A D; Peryt, W; Planeta, R; Pluta, J; Popov, B A; Posiadala, M; Przewlocki, P; Rauch, W; Ravonel, M; Renfordt, R; Röhrich, D; Rondio, E; Rossi, B; Roth, M; Rubbia, A; Rybczynski, M; Sadovskii, A; Sakashita, K; Schuster, T; Sekiguchi, T; Seyboth, P; Shibata, M; Sissakian, A N; Skrzypczak, E; Slodkowski, M; Sorin, A S; Staszel, P; Stefanek, G; Stepaniak, J; Strabel, C; Ströbele, H; Susa, T; Szentpétery, I; Szuba, M; Tada, M; Taranenko, A; Tsenov, R; Ulrich, R; Unger, M; Vassiliou, M; Vechernin, V V; Vesztergombi, G; Wlodarczyk, Z; Wojtaszek, A; Zipper, W; CERN. Geneva. SPS and PS Experiments Committee; SPSC

    2009-01-01

    This document presents the revised data taking schedule of NA61 with ion beams. The revision takes into account limitations due to the new LHC schedule as well as final results concerning the physics performance with secondary ion beams. It is proposed to take data with primary Ar and Xe beams in 2012 and 2014, respectively, and to test and use for physics a secondary B beam from primary Pb beam fragmentation in 2010, 2011 and 2013.

  5. WIPP conceptual design report. Addendum M. Computer system and data processing requirements for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Young, R.

    1977-06-01

    Data-processing requirements for the Waste Isolation Pilot Plant (WIPP) dictate a computing system that can provide a wide spectrum of data-processing needs on a 24-hour-day basis over an indeterminate time. A computer system is defined as a computer or computers complete with all peripheral equipment and extensive software and communications capabilities, including an operating system, compilers, assemblers, loaders, etc., all applicable to real-world problems. The computing system must be extremely reliable and easily expandable in both hardware and software to provide for future capabilities with a minimum impact on the existing applications software and operating system. The computer manufacturer or WIPP operating contractor must provide continuous on-site computer maintenance (maintain an adequate inventory of spare components and parts to guarantee a minimum mean-time-to-repair of any portion of the computer system). The computer operating system or monitor must process a wide mix of application programs and languages, yet be readily changeable to obtain maximum computer usage. The WIPP computing system must handle three general types of data processing requirements: batch, interactive, and real-time. These are discussed. Data bases, data collection systems, scientific and business systems, building and facilities, remote terminals and locations, and cables are also discussed

  6. On the evolution of the regulatory guidance for seismic qualification of electric and active mechanical equipment for nuclear power plants

    International Nuclear Information System (INIS)

    Ng, Ching Hang; Chen, Pei-Ying

    2009-01-01

    All electric and active mechanical equipment important to safety for nuclear power plants must be seismically qualified by testing, analysis, or combined analysis and testing. The general requirements for seismic qualification of electric and active mechanical equipment in nuclear power plants are delineated in Appendix S, 'Earthquake Engineering Criteria for Nuclear Power Plants,' to Title 10, Part 50, 'Domestic Licensing of Production and Utilization Facilities,' of the Code of Federal Regulations (10 CFR Part 50), item 52.47(20) of 10 CFR 52.47, 'Contents of Applications; Technical Information,' and Appendix A, 'Seismic and Geologic Siting Criteria for Nuclear Power Plants,' to 10 CFR Part 100, 'Reactor Site Criteria.' The United States Nuclear Regulatory Commission (NRC) issued Revision 2 of Regulatory Guide (RG) 1.100, 'Seismic Qualification of Electric and Mechanical for Nuclear Power Plants' in 1988, which endorsed, with restrictions, exceptions, and clarifications, Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 'IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,' for use in seismic qualification of both electric and mechanical equipment. In 2008, the staff at the NRC drafted Revision 3 of RG 1.100 to endorse, with restrictions, exceptions, and clarifications, the IEEE Std 344-2004 and the American Society of Mechanical Engineers (ASME) QME-1-2007 'Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.' IEEE Std 344-2004 was an update of Std 344-1987 and ASME QME-1-2007 was an update of QME-1-2002. The major changes in IEEE Std 344-2004 and ASME QME-1-2007 include the update and expansion of criteria and procedures describing the use of experience data as a method for seismic qualification of Class 1E electric equipment (including I and C components) as well as active mechanical equipment. In this paper, the staff will compare the draft Revision 3 to

  7. Proposal to negotiate the renewal of two blanket purchase contracts for the supply of automation systems and fieldbus equipment

    CERN Document Server

    2005-01-01

    This document concerns the renewal of two blanket purchase contracts for the supply of automation systems and fieldbus equipment for the CERN accelerators, technical services and experiments. The Finance Committee is invited to agree to the negotiation of the renewal of two blanket purchase contracts with SCHNEIDER ELECTRIC (FR) and SIEMENS SUISSE (CH) for the supply of automation systems and fieldbus equipment for a period of three years. The total annual amount covering both contracts will not exceed 3 000 000 Swiss francs, subject to revision for inflation.

  8. Additional Equipment for Soil Biodegradation

    Science.gov (United States)

    Vondráčková, Terezie; Kraus, Michal; Šál, Jiří

    2017-12-01

    Intensification of industrial production, increasing citizens’ living standards, expanding the consumer assortment mean in the production - consumption cycle a constantly increasing occurrence of waste material, which by its very nature must be considered as a source of useful raw materials in all branches of human activity. In addition to strict legislative requirements, a number of circumstances characterize waste management. It is mainly extensive transport associated with the handling and storage of large volumes of substances with a large assortment of materials (substances of all possible physical and chemical properties) and high demands on reliability and time coordination of follow-up processes. Considerable differences in transport distances, a large number of sources, processors and customers, and not least seasonal fluctuations in waste and strong price pressures cannot be overlooked. This highlights the importance of logistics in waste management. Soils that are contaminated with oil and petroleum products are hazardous industrial waste. Methods of industrial waste disposal are landfilling, biological processes, thermal processes and physical and chemical methods. The paper focuses on the possibilities of degradation of oil pollution, in particular biodegradation by bacteria, which is relatively low-cost among technologies. It is necessary to win the fight with time so that no ground water is contaminated. We have developed two additional devices to help reduce oil accident of smaller ranges. In the case of such an oil accident, it is necessary to carry out the permeability test of contaminated soil in time and, on this basis, to choose the technology appropriate to the accident - either in-sit biodegradation - at the site of the accident, or on-sit - to remove the soil and biodegrade it on the designated deposits. A special injection drill was developed for in-sit biodegradation, tossing and aeration equipment of the extracted soil was developed for

  9. Lunar construction/mining equipment

    Science.gov (United States)

    Ozdemir, Levent

    1990-01-01

    For centuries, mining has utilized drill and blast as the primary method of rock excavation. Although this technique has undergone significant improvements, it still remains a cyclic, labor intensive operation with inherent safety hazards. Other drawbacks include damage to the surrounding ground, creation of blast vibrations, rough excavation walls resulting in increased ventilation requirements, and the lack of selective mining ability. Perhaps the most important shortcoming of drill and blast is that it is not conducive to full implementation of automation or robotics technologies. Numerous attempts have been made in the past to automate drill and blast operations to remove personnel from the hazardous work environment. Although most of the concepts devised look promising on paper, none of them was found workable on a sustained production basis. In particular, the problem of serious damage to equipment during the blasting cycle could not be resolved regardless of the amount of charge used in excavation. Since drill and blast is not capable of meeting the requirements of a fully automated rock fragmentation method, its role is bound to gradually decrease. Mechanical excavation, in contrast, is highly suitable to automation because it is a continuous process and does not involve any explosives. Many of the basic principles and trends controlling the design of an earth-based mechanical excavator will hold in an extraterrestrial environment such as on the lunar surface. However, the economic and physical limitations for transporting materials to space will require major rethinking of these machines. In concept, then, a lunar mechanical excavator will look and perform significantly different from one designed for use here on earth. This viewgraph presentation gives an overview of such mechanical excavator systems.

  10. Introductory Business Textbook Revision Cycles: Are They Getting Shorter?

    Science.gov (United States)

    Zinser, Brian; Brunswick, Gary

    2010-01-01

    The rate of textbook revision cycles is examined in light of the recent trend towards more rapid revisions (and adoptions of textbooks). The authors conduct background research to better understand the context for textbook revision cycles and the environmental forces that have been influencing what appears to be more rapid textbook revisions. A…

  11. Nevada Test Site Radiological Control Manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  12. Revision of the DELFIC Particle Activity Module

    Energy Technology Data Exchange (ETDEWEB)

    Hooper, David A [ORNL; Jodoin, Vincent J [ORNL

    2010-09-01

    The Defense Land Fallout Interpretive Code (DELFIC) was originally released in 1968 as a tool for modeling fallout patterns and for predicting exposure rates. Despite the continual advancement of knowledge of fission yields, decay behavior of fission products, and biological dosimetry, the decay data and logic of DELFIC have remained mostly unchanged since inception. Additionally, previous code revisions caused a loss of conservation of radioactive nuclides. In this report, a new revision of the decay database and the Particle Activity Module is introduced and explained. The database upgrades discussed are replacement of the fission yields with ENDF/B-VII data as formatted in the Oak Ridge Isotope Generation (ORIGEN) code, revised decay constants, revised exposure rate multipliers, revised decay modes and branching ratios, and revised boiling point data. Included decay logic upgrades represent a correction of a flaw in the treatment of the fission yields, extension of the logic to include more complex decay modes, conservation of nuclides (including stable nuclides) at all times, and conversion of key variables to double precision for nuclide conservation. Finally, recommended future work is discussed with an emphasis on completion of the overall radiation physics upgrade, particularly for dosimetry, induced activity, decay of the actinides, and fractionation.

  13. Revision surgery for failed thermal capsulorrhaphy.

    Science.gov (United States)

    Park, Hyung Bin; Yokota, Atsushi; Gill, Harpreet S; El Rassi, George; McFarland, Edward G

    2005-09-01

    With the failure of thermal capsulorrhaphy for shoulder instability, there have been concerns with capsular thinning and capsular necrosis affecting revision surgery. To report the findings at revision surgery for failed thermal capsulorrhaphy and to evaluate the technical effects on subsequent revision capsular plication. Case series; Level of evidence, 4. Fourteen patients underwent arthroscopic evaluation and open reconstruction for a failed thermal capsulorrhaphy. The cause of the failure, the quality of the capsule, and the ability to suture the capsule were recorded. The patients were evaluated at follow-up for failure, which was defined as recurrent subluxations or dislocations. The origin of the instability was traumatic (n = 6) or atraumatic (n = 8). At revision surgery in the traumatic group, 4 patients sustained failure of the Bankart repair with capsular laxity, and the others experienced capsular laxity alone. In the atraumatic group, all patients experienced capsular laxity as the cause of failure. Of the 14 patients, the capsule quality was judged to be thin in 5 patients and ablated in 1 patient. A glenoid-based capsular shift could be accomplished in all 14 patients. At follow-up (mean, 35.4 months; range, 22 to 48 months), 1 patient underwent revision surgery and 1 patient had a subluxation, resulting in a failure rate of 14%. Recurrent capsular laxity after failed thermal capsular shrinkage is common and frequently associated with capsular thinning. In most instances, the capsule quality does not appear to technically affect the revision procedure.

  14. Addendum to: Modelling duality between bound and resonant meson spectra by means of free quantum motions on the de Sitter space-time dS{sub 4}

    Energy Technology Data Exchange (ETDEWEB)

    Kirchbach, M. [Instituto de Fisica, UASLP, San Luis Potosi (Mexico); Compean, C.B. [Instituto Tecnologico de San Luis Potosi, Soledad de Graciano Sanchez (Mexico)

    2017-04-15

    In the article under discussion the analysis of the spectra of the unflavored mesons lead us to some intriguing insights into the possible geometry of space-time outside the causal Minkowski light cone and into the nature of strong interactions. In applying the potential theory concept of geometrization of interactions, we showed that the meson masses are best described by a confining potential composed by the centrifugal barrier on the three-dimensional spherical space, S{sup 3}, and of a charge-dipole potential constructed from the Green function to the S{sup 3} Laplacian. The dipole potential emerged in view of the fact that S{sup 3} does not support single-charges without violation of the Gauss theorem and the superposition principle, thus providing a natural stage for the description of the general phenomenon of confined charge-neutral systems. However, in the original article we did not relate the charge-dipoles on S{sup 3} to the color neutral mesons, and did not express the magnitude of the confining dipole potential in terms of the strong coupling α{sub S} and the number of colors, N{sub c}, the subject of the addendum. To the amount S{sup 3} can be thought of as the unique closed space-like geodesic of a four-dimensional de Sitter space-time, dS{sub 4}, we hypothesized the space-like region outside the causal Einsteinian light cone (it describes virtual processes, among them interactions) as the (1+4)-dimensional subspace of the conformal (2+4) space-time, foliated with dS{sub 4} special relativity for strong interaction processes. The potential designed in this way predicted meson spectra of conformal degeneracy patterns, and in accord with the experimental observations. We now extract the α{sub s} values in the infrared from data on meson masses. The results obtained are compatible with the α{sub s} estimates provided by other approaches. (orig.)

  15. Safety equipment list for the light duty utility arm system

    International Nuclear Information System (INIS)

    Barnes, G.A.

    1998-01-01

    The initial issue (Revision 0) of this Safety Equipment List (SEL) for the Light Duty Utility Arm (LDUA) requires an explanation for both its existence and its being what it is. All LDUA documentation leading up to creation of this SEL, and the SEL itself, is predicated on the LDUA only being approved for use in waste tanks designated as Facility Group 3, i.e., it is not approved for use in Facility Group 1 or 2 waste tanks. Facility Group 3 tanks are those in which a spontaneous or induced hydrogen gas release would be small, localized, and would not exceed 25% of the LFL when mixed with the remaining air volume in the dome space; exceeding these parameters is considered unlikely. Thus, from a NFPA flammable gas environment perspective the waste tank interior is not classified as a hazardous location. Furthermore, a hazards identification and evaluation (HNF-SD-WM-HIE-010, REV 0) performed for the LDUA system concluded that the consequences of actual LDUA system postulated accidents in Flammable Gas Facility Group 3 waste tanks would have either NO IMPACT or LOW IMPACT on the offsite public and onsite worker. Therefore, from a flammable gas perspective, there is not a rationale for classifying any of SSCs associated with the LDUA as either Safety Class (SC) or Safety Significant (SS) SSCs, which, by default, categorizes them as General Service (GS) SSCs. It follows then, based on current PHMC procedures (HNF-PRO-704 and HNF-IP-0842, Vol IV, Section 5.2) for SEL creation and content, and from a flammable gas perspective, that an SEL is NOT REQ at sign D HOWEVER exclamation point exclamation point exclamation point There is both a precedent and a prudency to capture all SSCS, which although GS, contribute to a Defense-In-Depth (DID) approach to the design and use of equipment in potentially flammable gas environments. This Revision 0 of the LDUA SEL has been created to capture these SSCs and they are designated as GS-DID in this document. The specific reasons for

  16. Special Equipment and/or Devices.

    Science.gov (United States)

    National Sanitation Foundation, Ann Arbor, MI.

    This standard covers the sanitation requirements for equipment and/or devices used in the storage, preparation, or handling of foods and beverages. The National Sanitation Foundation's basic criteria for the evaluation of special equipment and/or devices has been prepared to fulfill several specific needs, its major function being to serve as a…

  17. 21 CFR 1250.67 - Watering equipment.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Watering equipment. 1250.67 Section 1250.67 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED... of drinking water or other beverages, or for food preservation purposes, equipment constructed so as...

  18. Using ADA Tasks to Simulate Operating Equipment

    Science.gov (United States)

    DeAcetis, Louis A.; Schmidt, Oron; Krishen, Kumar

    1990-01-01

    A method of simulating equipment using ADA tasks is discussed. Individual units of equipment are coded as concurrently running tasks that monitor and respond to input signals. This technique has been used in a simulation of the space-to-ground Communications and Tracking subsystem of Space Station Freedom.

  19. Enhancement of equipment services for Kozloduy NPP

    International Nuclear Information System (INIS)

    Schultz, Christophe

    2013-01-01

    Conclusion After 5 years of maintenance services, KNPP and AREVA have continuously intensified their partnership Close cooperation between KNPP, AREVA Local Office Engineers and OEM experts Involvement of sophisticated tools for diagnostics and condition monitoring Performance of engineering services and obsolescence evaluation Possibilities to perform equipment modernization of Electrical and IC equipment in future

  20. Emergency team personnel and technical equipment

    International Nuclear Information System (INIS)

    Muralt, R.

    1989-01-01

    The most important requirements for the emergency team can be summarized in three points. 1) The emergency team must be made up of top personnel from all fields and it should be functionally equiped. 2) The emergency teams must have complete command of their equipment. 3) The members of the team must be well motivated. 1 fig

  1. Weight/balance portable test equipment

    International Nuclear Information System (INIS)

    Whitlock, R.W.

    1994-01-01

    This document shows the general layout, and gives a part description for the weight/balance test equipment. This equipment will aid in the regulation of the leachate loading of tanker trucks. The report contains four drawings with part specifications. The leachate originates from lined trenches

  2. 7 CFR 550.38 - Equipment.

    Science.gov (United States)

    2010-01-01

    ... Regulations of the Department of Agriculture (Continued) AGRICULTURAL RESEARCH SERVICE, DEPARTMENT OF AGRICULTURE GENERAL ADMINISTRATIVE POLICY FOR NON-ASSISTANCE COOPERATIVE AGREEMENTS Management of Agreements... Agency, the Cooperator shall use the equipment to be replaced as trade-in or sell the equipment and use...

  3. Quantitative techniques for medical equipment maintenance management

    NARCIS (Netherlands)

    Ben Houria, Zeineb; Masmoudi, Malek; Al Hanbali, Ahmad; Khatrouch, Ikram; Masmoudi, Faouzi

    2016-01-01

    The maintenance department in a hospital is responsible for ensuring the safety of medical equipment and their availability while keeping the operation costs minimal. The selection of the best maintenance strategy is a key decision to reduce the equipment downtime, increase the availability, and

  4. 21 CFR 606.60 - Equipment.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 7 2010-04-01 2010-04-01 false Equipment. 606.60 Section 606.60 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) BIOLOGICS CURRENT... following frequency, include but are not limited to: Equipment Performance check Frequency Frequency of...

  5. Plutonium Immobilization Can Loading Equipment Review

    International Nuclear Information System (INIS)

    Kriikku, E.; Ward, C.; Stokes, M.; Randall, B.; Steed, J.; Jones, R.; Hamilton, L.

    1998-05-01

    This report lists the operations required to complete the Can Loading steps on the Pu Immobilization Plant Flow Sheets and evaluates the equipment options to complete each operation. This report recommends the most appropriate equipment to support Plutonium Immobilization Can Loading operations

  6. Radio monitoring problems, methods, and equipment

    CERN Document Server

    Rembovsky, Anatoly; Kozmin, Vladimir; Smolskiy, Sergey

    2009-01-01

    Offers a unified approach to fundamental aspects of Automated Radio Monitoring (ARM). This book discusses the development, modeling, design, and manufacture of ARM systems. It provides classification and descriptions of modern high-efficient hardware-software ARM equipment, including the equipment for detection and radio direction-finding.

  7. Development of Equipment for Use in Sport

    Science.gov (United States)

    James, David

    2012-01-01

    No one has ever been able to create a running shoe that can make one run faster, but in other sports the design of equipment has the potential to offer considerable enhancement. Judgement has to be made as to whether such advantage becomes unfair. This article indicates many possible sports in which the equipment plays an important part in the…

  8. 36 CFR 1207.32 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... 1207.32 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION GENERAL RULES... as follows: (1) Items of equipment with a current per-unit fair market value of less than $5,000 may...) Items of equipment with a current per unit fair market value in excess of $5,000 may be retained or sold...

  9. 21 CFR 211.65 - Equipment construction.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 4 2010-04-01 2010-04-01 false Equipment construction. 211.65 Section 211.65 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) DRUGS... construction. (a) Equipment shall be constructed so that surfaces that contact components, in-process materials...

  10. 47 CFR 18.203 - Equipment authorization.

    Science.gov (United States)

    2010-10-01

    ... information already on file with the Commission. (2) A technical report pursuant to §§ 18.207 and 18.311. (b... 47 Telecommunication 1 2010-10-01 2010-10-01 false Equipment authorization. 18.203 Section 18.203 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL INDUSTRIAL, SCIENTIFIC, AND MEDICAL EQUIPMENT...

  11. Addendum report of the JHPS expert committee on radiation protection of the lens of the eye (2). When and how should the dosimetry of beta H_p(3) be made?

    International Nuclear Information System (INIS)

    Akahane, Keiichi; Tatsuzaki, Hideo; Iimoto, Takeshi; Ichiji, Takeshi; Hamada, Nobuyuki; Iwai, Satoshi; Ohguchi, Hiroyuki; Ohno, Kazuko; Kawaura, Chiyo; Kurosawa, Tadahiro; Tsujimura, Norio; Hayashida, Toshiyuki; Hotta, Yutaka; Yamasaki, Tadashi; Yokoyama, Sumi

    2015-01-01

    In a mixed field of photon and beta radiations, the same dose assigned to skin is normally assigned to the dose to the lens of the eye as a conservative estimate of H_p(3). In exceptional cases where a very high beta dose might be imparted of the same order with the dose limit, however, the conservatively biased dose must be too limiting, and thereby an accurate estimate of beta H_p(3) is desirable. This addendum report of the Japan Health Physics Society Expert Committee on Radiation Protection of the Lens of the Eye presents a practical proposal of when and how the dosimetry of beta H_p(3) should be made. (author)

  12. Proposal for revisions of the United Nations Moon Treaty

    Science.gov (United States)

    Fernandes, Vera; Abreu, Neyda; Fritz, J.; Knapmeyer, Martin; Smeenk, Lisa; Ten Kate, Inge; Trüninger, Monica

    Valleys of Southern Victoria Land) will also be instrumental in improving the current Moon Treaty. To update the Moon Treaty, we propose the creation of a Council composed of a diverse group of individuals to ensure that this document will have broad, long-term impact. It will be an interdisciplinary endeavour that needs to bring together natural ("hard") sciences, social sciences, and humanities to produce a sensitive and thorough document. Most importantly, it will be imperative to change the current status on the use of lunar resources, as it will certainly destroy the pristine environment the Moon presents. There-fore, we are currently at a very important time to reconsider the U.N. Moon Treaty and make all the necessary amendments and addendums that will assure the preservation of the Moon while at the same time maximizing the amount of scientific data acquired from, of, and on the Moon [the Earth and the Solar System] from this natural information storage (e.g., impact flux since the early Solar System, formation and differentiation of a large planetary body). The goal of the revision of the Moon Treaty is three fold: (1) the preservation of the existing in-formation existing the Moon regarding the formation and evolution of the Earth and the inner early Solar System, while at the same time maximizing the scientific data acquisition, (2) the promotion and improvement of the international cooperation in science and, technology, and (3) balance and regulate the competing scientific, economic, strategic and cultural interests. This will assure that future generations will still be able to take advantage of the pristine Moon and further explore it. In order to be most effective the responsibilities drawn in the new doc-ument(s) should be reformed into an agreement, which shall be abided by all nations, private enterprises, multi-nationals and individuals who do not. As first step in reaching this goal the current, rather failed, treaty (most of the Moon-faring nations

  13. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young

    2016-01-01

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety

  14. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety.

  15. Automatic monitoring of vibration welding equipment

    Science.gov (United States)

    Spicer, John Patrick; Chakraborty, Debejyo; Wincek, Michael Anthony; Wang, Hui; Abell, Jeffrey A; Bracey, Jennifer; Cai, Wayne W

    2014-10-14

    A vibration welding system includes vibration welding equipment having a welding horn and anvil, a host device, a check station, and a robot. The robot moves the horn and anvil via an arm to the check station. Sensors, e.g., temperature sensors, are positioned with respect to the welding equipment. Additional sensors are positioned with respect to the check station, including a pressure-sensitive array. The host device, which monitors a condition of the welding equipment, measures signals via the sensors positioned with respect to the welding equipment when the horn is actively forming a weld. The robot moves the horn and anvil to the check station, activates the check station sensors at the check station, and determines a condition of the welding equipment by processing the received signals. Acoustic, force, temperature, displacement, amplitude, and/or attitude/gyroscopic sensors may be used.

  16. Requirements for industrial x-ray equipment

    International Nuclear Information System (INIS)

    1987-01-01

    This safety code is concerned with the protection of all individuals who may be exposed to radiation emitted by X-ray equipment operating at energies up to 1 MeV as used in industrial radiography. This code presents basic radiation safety information for the protection of personnel operating and servicing X-ray equipment and other workers and the general public in the vicinity of areas where X-ray equipment is in operation. It specifies general safety features of design, construction and functioning of X-ray equipment and facilities; describes the responsibilities of the user, operator and maintenance personnel; contains recommendations to ensure that the X-ray equipment is used and maintained in accordance with the ALARA principle; and describes a program of personnel monitoring and radiation safety surveys. ( 6 refs., 5 tabs., 4 figs.)

  17. Equipment qualification research program: program plan

    International Nuclear Information System (INIS)

    Dong, R.G.; Smith, P.D.

    1982-01-01

    The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump

  18. Development of Turbulence-Measuring Equipment

    Science.gov (United States)

    Kovasznay, Leslie S G

    1954-01-01

    Hot wire turbulence-measuring equipment has been developed to meet the more stringent requirements involved in the measurement of fluctuations in flow parameters at supersonic velocities. The higher mean speed necessitates the resolution of higher frequency components than at low speed, and the relatively low turbulence level present at supersonic speed makes necessary an improved noise level for the equipment. The equipment covers the frequency range from 2 to about 70,000 cycles per second. Constant-current operation is employed. Compensation for hot-wire lag is adjusted manually using square-wave testing to indicate proper setting. These and other features make the equipment adaptable to all-purpose turbulence work with improved utility and accuracy over that of older types of equipment. Sample measurements are given to demonstrate the performance.

  19. Oil and gas products and energy equipment

    International Nuclear Information System (INIS)

    1996-01-01

    The planned activities of the Canadian oil and gas products and energy equipment industry for 1996-1997, were presented. The sector is made up of approximately 1500 small and medium sized enterprises. The Canadian oil field manufacturing and servicing industry holds only a small 2.5% share of the world export market, but it is recognized internationally as one of the leading suppliers of advanced petroleum equipment. Their exports include specialized equipment for extracting oil sands, gathering and treatment facilities for sour gas, underbalanced drilling technologies, equipment for wells experiencing declining production rates, top motor drives, winter drilling rigs, and horizontal drilling technologies. They also offer petroleum industry software products. Most exploration and production equipment sold abroad by Canadian firms is manufactured in Canada, but there is an increasing trend toward manufacturing in the country of operation. 2 tabs

  20. Equipment for the handling of thorium materials

    International Nuclear Information System (INIS)

    Heisler, S.W. Jr.; Mihalovich, G.S.

    1988-01-01

    The Feed Materials Production Center (FMPC) is the United States Department of Energy's storage facility for thorium. FMPC thorium handling and overpacking projects ensure the continued safe handling and storage of the thorium inventory until final disposition of the materials is determined and implemented. The handling and overpacking of the thorium materials requires the design of a system that utilizes remote handling and overpacking equipment not currently utilized at the FMPC in the handling of uranium materials. The use of remote equipment significantly reduces radiation exposure to personnel during the handling and overpacking efforts. The design system combines existing technologies from the nuclear industry, the materials processing and handling industry and the mining industry. The designed system consists of a modified fork lift truck for the transport of thorium containers, automated equipment for material identification and inventory control, and remote handling and overpacking equipment for material identification and inventory control, and remote handling and overpacking equipment for repackaging of the thorium materials

  1. Contractors Road Heavy Equipment Area SWMU 055 Corrective Measures Implementation Progress Report

    Science.gov (United States)

    Dorman, Lane

    2015-01-01

    This Corrective Measures Implementation (CMI) Progress Report, Revision 1, for Contractor's Road Heavy Equipment (CRHE) Area Solid Waste Management Unit (SWMU) Number 055 was prepared by Geosyntec Consultants (Geosyntec) for the National Aeronautics and Space Administration (NASA) under contract number NNK09CA02B, Delivery Order NNK09CA62D and Project Number PCN ENV-2324. This CMI Progress Report documents: (i) activities conducted as part of supplemental assessment activities completed from June 2009 through November 2014; (ii) Engineering Evaluation (EE) Advanced Data Packages (ADPs); and (iii) recommendations for future activities related to corrective measures at the Site.

  2. Emergency preparedness in Finland: improvement of the measurement equipment used in the assessment of internal doses

    Energy Technology Data Exchange (ETDEWEB)

    Muikku, M.; Rahola, T. [STUK - Radiation and nuclear safety authority, Helsinki (Finland)

    2006-07-01

    The need for assessing internal radiation doses in emergency situations is evident. Internal exposure can be assessed using direct measurement results or by using information on activity concentrations in inhaled air and in foodstuffs combined with inhalation and consumption data. As a part of the continuous improving of emergency preparedness in Finland, S.T.U.K. - Radiation and Nuclear Safety Authority has obtained 35 monitors for thyroid measurements in field conditions and initiated a project to revise the radiation measurement equipment in local food and environmental laboratories. (authors)

  3. Energy to the Edge (E2E) Equipment Assessment U.S. Army Rapid Equipping Force

    Science.gov (United States)

    2015-05-01

    84 Contents Energy to the Edge • U.S. Army Rapid Equipping Force U.S. Army Rapid Equipping Force 1.0 Executive Summary Executive Summary U.S. Army... audiovisual equipment. • Once radiant barrier liner is inserted, the process of subsequent setups • Cables for lighting and outlets are located...behind the internal barrier • The shelter comes with organic audiovisual equipment. b. • • This shelter has a different setup and tear down process

  4. Days individual equipment of protection and professional risks; Equipements de protection individuelle et risques professionnelles

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The personal protection equipment is studied in the legal way (legal liabilities, certification, European texts), technical way (ergonomics, painfulness of ventilated equipment wearing, reliability of a respirable air line, protection gloves against the chemical risk, exposure to nano particulates, working in hot area), human factors (hostile area and emotion management), studies on personal equipment such evaluation, efficiency, conception of new equipment, physiological tolerance, limit of use, and some general safety studies on the working places. (N.C.)

  5. The tendency of medical electrical equipment - IEC 60601-2-54: Particular requirements for the basic safety and essential performance of x-ray equipment for radiography and radioscopy

    International Nuclear Information System (INIS)

    Roh, Young Hoon; Kim, Jung Min

    2015-01-01

    Medical electrical equipment - Part 1: General requirement for basic safety and essential performance of MFDS was revised as 3th edition and Medical electrical equipment Part 2-54: Particular requirements for the basic safety and essential performance of X-ray equipment will be expected to be announced as notification. Therefore this technical report was written to introduce provision of the particular requirements, replacement, addition, amendment. The purpose of this particular requirements is to secure requirements for basic safety and essential performance of X-ray equipment for radiography and radioscopy. X-ray high voltage generator, mechanical protective device, protection against radiation is included in this particular requirements. Medical electrical equipment - Part 1, Part 1-2, Part 1-3 is applied to this particular requirements. If the requirements is announced as notification, It is expected to widen understanding for basic safety and essential performance of X-ray equipment for radiography and radioscopy and play a part to internationalize of medical equipment

  6. Establishment of nuclear equipment qualification system

    International Nuclear Information System (INIS)

    Joo, Po Kook; Lim, Nam Jin; Lee, Young Gun

    2003-04-01

    This study is carried out by KEARI(Korea Atomic Energy Research Institute) as the lead organization in cooperation with KIMM(Korea Institute of Machinery and Materials), KTL(Korea Testing Laboratory) and KRISS(Korea Research Institute of Standards and Science) to construct a basis of efficient management of nuclear equipment qualification business by expanding test equipment of each of participating organization, and developing qualification technologies. As for KIMM, control system of large scale shaker was replaced with advanced system, and LOCA(Loss of Coolant Accident) test facility was installed. KTL is now capable of conducting seismic tests of nuclear I and C as a result of installation of seismic test equipment during the first two project years. KRISS participated in the Project with a view to have large scale EMI test equipment and related technologies. In parallel with expansion of test equipment, a industrial-educational-research cooperation committee, as an intermediate step toward integrated equipment qualification system to maximize the usage of test equipment, was established and cooperation methods were investigated. As a result, Korea Nuclear Equipment Qualification Association, an corporate juridical person, was established. Research on development of thermal and radiation aging test technology of nuclear materials was carried out by Hanyang University and SECO(Saehan Engineering and Qualification Co., Ltd.). Integrated Equipment Qualification Database was developed which contains material test data, equipment qualification data and other EQ related informations. Standard qualification procedures were developed in order for test laboratories and manufacturers to establish design requirements and to efficiently perform tests

  7. Equipment Reliability Program in NPP Krsko

    International Nuclear Information System (INIS)

    Skaler, F.; Djetelic, N.

    2006-01-01

    Operation that is safe, reliable, effective and acceptable to public is the common message in a mission statement of commercial nuclear power plants (NPPs). To fulfill these goals, nuclear industry, among other areas, has to focus on: 1 Human Performance (HU) and 2 Equipment Reliability (EQ). The performance objective of HU is as follows: The behaviors of all personnel result in safe and reliable station operation. While unwanted human behaviors in operations mostly result directly in the event, the behavior flaws either in the area of maintenance or engineering usually cause decreased equipment reliability. Unsatisfied Human performance leads even the best designed power plants into significant operating events, which can be found as well-known examples in nuclear industry. Equipment reliability is today recognized as the key to success. While the human performance at most NPPs has been improving since the start of WANO / INPO / IAEA evaluations, the open energy market has forced the nuclear plants to reduce production costs and operate more reliably and effectively. The balance between these two (opposite) goals has made equipment reliability even more important for safe, reliable and efficient production. Insisting on on-line operation by ignoring some principles of safety could nowadays in a well-developed safety culture and human performance environment exceed the cost of electricity losses. In last decade the leading USA nuclear companies put a lot of effort to improve equipment reliability primarily based on INPO Equipment Reliability Program AP-913 at their NPP stations. The Equipment Reliability Program is the key program not only for safe and reliable operation, but also for the Life Cycle Management and Aging Management on the way to the nuclear power plant life extension. The purpose of Equipment Reliability process is to identify, organize, integrate and coordinate equipment reliability activities (preventive and predictive maintenance, maintenance

  8. Evaluation of the revised electrolytic reduction reactor from a remote operability aspect

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyo Jik; Yoon, K. H.; Kim, K. H. (and others)

    2008-01-15

    This report presents an evaluation of the remote operability of the revised electrolytic reduction (ER) reactor installed in the ACP at KAERI. All operations have to be implemented in a fully remote manner since the ACPF is a hotcell for handling highly radioactive materials such as spent nuclear fuels. In particular, the ER process is a key process of the Advanced spent fuel Conditioning Process (ACP) and it needs a lot of other auxiliary equipment to perform it. Also, since the ER equipment is too big and complicated, and contrarily the ACPF is not big enough, and one common rail is allotted for a bridge transported servo manipulator, an in-cell crane and a gate crane, a remote handling of the ER reactor is accompanied by a difficulty for a remote operation. For an easy understanding, short overview of the ER process, the remote handling equipment, the structural configuration of the ACPF and the detail drawings of the ER equipment are presented. Through 4 month-remote operational tests, detailed operational procedures are presented along with pictures. The remote handling equipment and tools required in each operation are addressed in detail. Also, the procedure to implement each remote operation, and a task difficulty are evaluated from a remote operability aspect. All the remote tasks are distinguished according to whether a remote operation can be performed or not. Finally, partial improvement or an idea to solve the suggested problems is presented. This report will assist in modifying or scaling up the ER reactor.

  9. Bilateral and multilateral agreements and other arrangements in Europe and North America on the protection and use of transboundary waters. Addendum. 1994 Update

    International Nuclear Information System (INIS)

    1995-01-01

    The present document is issued pursuant to the decision taken by the Committee on Environmental Policy at its first session (ECE/CEP/1) to revise and update annually the 1993 list of Bilateral and Multilateral Agreements and Other Arrangements in Europe and North America on the Protection and Use of Transboundary Waters (ECE/ENVWA/32) and to publish a completely revised and updated version of the consolidated list of agreements at three-yearly intervals. By 31 December 1994, additions and amendments to this document had been submitted by the delegations of Austria, Croatia, Netherlands, Russian Federation and Slovakia. These have been incorporated into the present document

  10. Postoperative pain outcomes after transvaginal mesh revision.

    Science.gov (United States)

    Danford, Jill M; Osborn, David J; Reynolds, W Stuart; Biller, Daniel H; Dmochowski, Roger R

    2015-01-01

    Although the current literature discusses mesh complications including pain, as well as suggesting different techniques for removing mesh, there is little literature regarding pain outcomes after surgical removal or revision. The purpose of this study is to determine if surgical removal or revision of vaginal mesh improves patient's subjective complaints of pelvic pain associated with original placement of mesh. After obtaining approval from the Vanderbilt University Medical Center Institutional Review Board, a retrospective review of female patients with pain secondary to previous mesh placement who underwent excision or revision of vaginal mesh from January 2000 to August 2012 was performed. Patient age, relevant medical history including menopause status, previous hysterectomy, smoking status, and presence of diabetes, fibromyalgia, interstitial cystitis, and chronic pelvic pain, was obtained. Patients' postoperative pain complaints were assessed. Of the 481 patients who underwent surgery for mesh revision, removal or urethrolysis, 233 patients met our inclusion criteria. One hundred and sixty-nine patients (73 %) reported that their pain improved, 19 (8 %) reported that their pain worsened, and 45 (19 %) reported that their pain remained unchanged after surgery. Prior history of chronic pelvic pain was associated with increased risk of failure of the procedure to relieve pain (OR 0.28, 95 % CI 0.12-0.64, p = 0.003). Excision or revision of vaginal mesh appears to be effective in improving patients' pain symptoms most of the time. Patients with a history of chronic pelvic pain are at an increased risk of no improvement or of worsening pain.

  11. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    International Nuclear Information System (INIS)

    Bierschbach, M.C.; Haffner, D.R.; Schneider, K.J.; Short, S.M.

    2002-01-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of 3 H-labeled compounds; a laboratory for the manufacture of 14 C-labeled compounds; a laboratory for the manufacture of 123 I-labeled compounds; a laboratory for the manufacture of 137 Cs sealed sources; a laboratory for the manufacture of 241 Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires

  12. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  13. Drawing Evaluation Report for Sampling Equipment Drawings

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This document presents the results of a task to update the evaluation of River Protection Project (WP) sampling equipment drawings and updates the assigned drawings category as either essential, support, or general drawings. This report updates the drawing evaluation that was originally done per Engineering Task Plan For Truck 3 and 4 Drawing Compliance and Evaluation. The scope of this report is limited to updating the evaluation and identification of drawing category for drawings of certain tank waste sampling equipment for which the RPP Characterization Project has been assigned custody, including: vapor sampling, grab sampling, auger sampling, all core sampling equipment, and Light Duty Utility Arm (LDUA) (see LMHC contract No. 519, release 10). This report does not address drawings for other waste tank deployed equipment systems having similar assigned custody, such as, Cone Penetrometer system, or Long Length Contaminated Equipment (LLCE). The Cone Penetrometer system, which is depicted on vendor drawings, (not H- series), is not currently turned over to operations for deployment. The LLCE equipment was just recently assigned to Characterization Project and was not included in the original scope for this update and will be addressed in the evaluation update scheduled for later in fiscal year 1999, when equipment ownership is determined

  14. Drawing evaluation report for sampling equipment drawings

    International Nuclear Information System (INIS)

    WILSON, G.W.

    1999-01-01

    This document presents the results of a task to evaluate Tank Waste Remediation System (TWRS) sampling equipment drawings and identifies drawings category as either essential, support, or general drawings. This report completes the drawing evaluation task as outlined in Engineering Task Plan For Truck 3 and 4 Drawing Compliance and Evaluation (Wilson, 1997). The scope of this report is limited to an evaluation and identification of drawing category for drawings of certain tank waste sampling equipment for which the TRWS Characterization Project has been assigned custody, including: vapor sampling, grab sampling, auger sampling, and all core sampling equipment (see LMHC Task Order 304). This report does not address drawings for other waste tank deployed equipment systems having similar assigned custody, such as, Light Duty Utility Arm (LDUA), Cone Penetrometer system, or Long Length Contaminated Equipment (LLCE). The LDUA drawings are addressed in the Characterization Equipment Essential Drawings (HNF 1998). The Cone Penetrometer system drawings which are vendor drawings (not H- series) is not currently turned over to operations for deployment. The LLCE equipment was just recently assigned to Characterization Project and were not included in the original scope for this evaluation and will be addressed in the evaluation update scheduled for fiscal year 1999

  15. Progress on EPRI electrical equipment qualification research

    International Nuclear Information System (INIS)

    Sliter, G.E.

    1983-01-01

    The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

  16. Long Length Contaminated Equipment Maintenance Plan

    International Nuclear Information System (INIS)

    ESVELT, C.A.

    2000-01-01

    The purpose of this document is to provide the maintenance requirements of the Long Length Contaminated Equipment (LLCE) trailers and provide a basis for the maintenance frequencies selected. This document is applicable to the LLCE Receiver trailer and Transport trailer assembled by Mobilized Systems Inc. (MSI). Equipment used in conjunction with, or in support of, these trailers is not included. This document does not provide the maintenance requirements for checkout and startup of the equipment following the extended lay-up status which began in the mid 1990s. These requirements will be specified in other documentation

  17. Remote handling equipment for CANDU retubing

    International Nuclear Information System (INIS)

    Crawford, G.S.; Lowe, H.

    1993-01-01

    Numet Engineering Ltd. has designed and supplied remote handling equipment for Ontario Hydro's retubing operation of its CANDU reactors at the Bruce Nuclear Generating Station. This equipment consists of ''Retubing Tool Carriers'' an'' Worktables'' which operate remotely or manually at the reactor face. Together they function to transport tooling to and from the reactor face, to position and support tooling during retubing operations, and to deliver and retrieve fuel channels and channel components. This paper presents the fundamentals of the process and discusses the equipment supplied in terms of its design, manufacturing, components and controls, to meet the functional and quality requirements of Ontario Hydro's retubing process. (author)

  18. Equipment for x- and gamma ray radiography

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    The following topics related to the equipment for x - and gamma ray radiography are discussed in this chapter. The topics are x-ray source for Industrial Radiography: properties of x-ray, generation of x-ray, mechanism of x-ray production, x-ray equipment, power supply, distribution of x-ray intensity along the tube: gamma ray source for Industrial Radiography: properties of gamma rays, gamma ray sources, gamma ray projectors on cameras, source changing. Care of Radiographic Equipments: Merits and Demerits of x and Gamma Rays

  19. Exposure parameters in fluoroscopy equipment. Quality control

    International Nuclear Information System (INIS)

    Alonso, M.; Castaneda, M.J.; Matorras, P.; Diaz-Caneja, N.; Gutierrez, I.

    1992-01-01

    Within the quality control program in Diagnostic Radiology currently being undertaken at the 'Marques de Valdecilla' University Hospital, the corresponding specification and procedure prototypes for the control of conventional radioscopy equipment have been elaborated and applied. This paper presents the values proposed in the specifications and those obtained for the following radioscopy equipment parameters: reference kerma, and its reproducibility, kerma linearity, maximum kerma at the skin, and total filtration. The results obtained indicate that the equipment studied could comply with specified requirements if a Maintenance Program were to be implemented in coordination with the Quality Control Program. (author)

  20. LMZ experience in refurbishment of hydroturbine equipment

    Energy Technology Data Exchange (ETDEWEB)

    Sotnikov, Anatoly A. [LMZ, St. Petersburg (Russian Federation). Div. of Hydraulic Machine

    2000-07-01

    AO LMZ experience in refurbishment of hydroturbine equipment is generalized. Hydraulic turbines of many power stations having been in service of more than 30 years need rehabilitation and modernization. As a rule, the following problems are solved in the process of refurbishment works: increase of turbine efficiency and output, ensuring of reliable operation of the equipment during the next length of life, ensuring the environmental safety of the equipment, furnishing of the power station with up to date automatic control systems. The process of refurbishment used by LMZ is described. The examples of refurbishment are given. (author)