Detailed description of an SSAC at the facility level for mixed oxide fuel fabrication facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-09-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a mixed oxide fuel fabrication facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Hanford Site existing irradiated fuel storage facilities description

Energy Technology Data Exchange (ETDEWEB)

Willis, W.L.

1995-01-11

This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-11-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Description of an engineering-scale facility for uranium fluorination studies

International Nuclear Information System (INIS)

Yagi, Eiji; Saito, Shinichi; Horiuchi, Masato

1976-03-01

In the research program of power reactor fuel reprocessing by fluoride volatility process, the engineering facility was constructed to establish the techniques of handling kilogram quantities of fluorine and uranium hexafluoride and to obtain engineering data on the uranium fluidized-bed oxidation and fluorination. This facility is designed for a capacity of 5 kg per batch. Descriptions on the facility and equipment are given, including design philosophy, safety and its analysis. (auth.)

47 CFR 2.948 - Description of measurement facilities.

Science.gov (United States)

2010-10-01

... description of the measurement facilities employed. (1) If the measured equipment is subject to the... number; (v) FCC Registration Number (FRN); (vi) A statement as to whether or not the laboratory performs... supporting structures, and all structures within 5 times the distance between the measuring antenna and the...

Cold Vacuum Drying facility civil - structural system design description (SYS 06)

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document

Detailed description of an SSAC at the facility level for research reactors

International Nuclear Information System (INIS)

Jones, R.J.

1984-09-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.

1982-09-01

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

International Nuclear Information System (INIS)

Schneider, K.J.

1982-09-01

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation

Good ergonomic practices in a terminal facility

Energy Technology Data Exchange (ETDEWEB)

Anjos, Luciana Mattos dos; Curty, Adriana Favacho [CHEMTECH, Rio de Janeiro, RJ (Brazil); Franca, Guilherme Foerster do Monte; Jardino, Alessandro Neto [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)

2009-07-01

Ergonomics is the technological design of the interplay between men, machines and environment in order to make labor activities more pleasant, profitable and functional. This article analyses the importance of ergonomic issues in process terminal plants and facilities, since the conceptual design stage until the detail engineering design. The ergonomic solutions are compared with practices that are current in engineering design plants nowadays. It will be shown how an inadequate ergonomic design often leads to accessibility problems and non-effectiveness during plant operation and dangers in emergency situations. The way perform an ergonomic design is to integrate the various disciplines that are involved in all stages of the design plant. The earlier the ergonomic design is implemented the better are the results in cost reduction, since later design modifications are more time-consuming and expensive. (author)

BWR Full Integral Simulation Test (FIST) program: facility description report

International Nuclear Information System (INIS)

Stephens, A.G.

1984-09-01

A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

Energy Technology Data Exchange (ETDEWEB)

Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

2000-08-01

In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

Evalution of NDA techniques and instruments for assay of nuclear waste at a waste terminal storage facility

International Nuclear Information System (INIS)

Blakeman, E.D.; Allen, E.J.; Jenkins, J.D.

1978-05-01

The use of Nondestructive Assay (NDA) instrumentation at a nuclear waste terminal storage facility for purposes of Special Nuclear Material (SNM) accountability is evaluated. Background information is given concerning general NDA techniques and the relative advantages and disadvantages of active and passive NDA methods are discussed. The projected characteristics and amounts of nuclear wastes that will be delivered to a waste terminal storage facility are presented. Wastes are divided into four categories: High Level Waste, Cladding Waste, Intermediate Level Waste, and Low Level Waste. Applications of NDA methods to the assay of these waste types is discussed. Several existing active and passive NDA instruments are described and, where applicable, results of assays performed on wastes in large containers (e.g., 55-gal drums) are given. It is concluded that it will be difficult to routinely achieve accuracies better than approximately 10--30% with ''simple'' NDA devices or 5--20% with more sohpisticated NDA instruments for compacted wastes. It is recommended that NDA instruments not be used for safeguards accountability at a waste storage facility. It is concluded that item accountability methods be implemented. These conclusions and recommendations are detailed in a concurrent report entitled ''Recommendations on the Safeguards Requirements Related to the Accountability of Special Nuclear Material at Waste Terminal Storage Facilities'' by J.D. Jenkins, E.J. Allen and E.D. Blakeman

18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

Science.gov (United States)

2010-04-01

... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any Operation...

Kajian Kinerja Terminal Batu Ampar Kota Balikpapan

Directory of Open Access Journals (Sweden)

Randha Alief Chikita

2018-01-01

Full Text Available Batu Ampar Terminal Balikpapan is the only type A passenger terminal in Balikpapan City. The purpose of this study is to determine the operational performance of the terminal at this time and also to determine the level of service in the terminal. The results of this study indicate that for FIFO queue discipline analysis on AKDP and AKAP bus lines, it is known that ρ <1 means that there is currently no queue in the terminal. For the analysis of terminal facilities it is known that there are still some terminal facilities that are not yet available from the main facilities and supporting facilities, therefore the need for additional facilities in order to meet the standard of passenger terminal type A. In the next 15 years analysis for traffic intensity value is approaching 1 which means in the future will cause the queue in the terminal, so it is necessary for the improvement of terminal performance. For the service performance with IPA method there are 35 variables that there are 7 variables that enter in quadrant I. In the next step to do analysis to know the priority of handling by using QFD method. Keywords: Batu Ampar Terminal Balikpapan, IPA, terminal performance, QFD

Analytical methodology and facility description spent fuel policy

Energy Technology Data Exchange (ETDEWEB)

1978-08-01

Three generic environmental impact statements (GEISs) on domestic fuels, foreign fuels, and storage charges are being prepared to provide environmental input into decisions on whether, and if so how the 1977 Presidential policy on spent fuel storage should be implmented. This report provides background information for two of these environmental impact statements: Storage of U.S. Spent Power Reactor Fuel and Storage of Foreign Spent Power Reactor Fuel. It includes the analytical methodology used in GEISs to assess the environmental effects and a description of the facilities used in the two GEISs.

Analytical methodology and facility description spent fuel policy

International Nuclear Information System (INIS)

1978-08-01

Three generic environmental impact statements (GEISs) on domestic fuels, foreign fuels, and storage charges are being prepared to provide environmental input into decisions on whether, and if so how the 1977 Presidential policy on spent fuel storage should be implmented. This report provides background information for two of these environmental impact statements: Storage of U.S. Spent Power Reactor Fuel and Storage of Foreign Spent Power Reactor Fuel. It includes the analytical methodology used in GEISs to assess the environmental effects and a description of the facilities used in the two GEISs

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1998-11-30

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Cold Vacuum Drying Facility Crane and Hoist System Design Description. System 14

International Nuclear Information System (INIS)

TRAN, Y.S.

2000-01-01

This system design description (SDD) is for the Cold Vacuum Drying (CVD) Facility overhead crane and hoist system. The overhead crane and hoist system is a general service system. It is located in the process bays of the CVD Facility, supports the processes required to drain the water and dry the spent nuclear fuel (SNF) contained in the multi-canister overpacks (MCOs) after they have been removed from the K-Basins. The location of the system in the process bay is shown

NWTS conceptual reference repository description (CRRD). Volume 1. Summary

International Nuclear Information System (INIS)

1981-05-01

This report is a Conceptual Reference Repository Description (CRRD) for the terminal storage of spent, unreprocessed fuel assemblies and low-level transuranic waste. It is based on the following three previously prepared conceptual design reports: National Waste Terminal Storage in a Bedded Salt Formation for Spent Unreprocessed Fuel (NWTS-R2), prepared by Kaiser Engineers; National Waste Terminal Storage Repository Number 1 (NWTS-R1), prepared by Stearns-Roger; Spent Fuel Receiving and Packaging Facility Conceptual Design, prepared by Rockwell Hanford Operations and Kaiser Engineers. The CRRD is not itself a conceptual design report, but combines the key features of the above three reports into a description of a reference repository. This description is to be used as a basis for the preparation of a preliminary information report for the repositories. The CRRD discusses from a conceptual engineering standpoint the structures, systems, equipment, and operations necessary to (1) receive unreprocessed spent fuel assemblies via standard shipping casks, (2) offload these assemblies, (3) place the assemblies in canisters, (4) transport the canisters to underground storage locations in the salt dome, and (5) place these canisters in terminal storage. The CRRD also elaborates on the concepts for the retrieval and recovery of the spent fuel after burial; describes the development of the shafts and the underground areas,as well as the supporting operational utility and administrative features of the repository; and discusses the impacts on the reference repository of (1) changes in the waste package concept, (2) dry receiving and dry temporary storage of waste, (3) terminal storage of reprocessing waste, and (4) alternative underground development schemes

Operating manual for the High Flux Isotope Reactor. Description of the facility

Energy Technology Data Exchange (ETDEWEB)

None

1965-06-01

This report contains a comprehensive description of the High Flux Isotope Reactor facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procedures are presented in another report.

Detailed description of an SSAC at the facility level for light water moderated (off-load refueled) power reactor facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-03-01

This report is intended to provide the technical details of an effective State Systems of Accounting for and Control of Nuclear Material (SSAC) which Member States may use, if they wish, to establish and maintain their SSACs. It is expected that systems designed along the lines described would be effective in meeting the objectives of both national and international systems for nuclear material accounting and control. This document accordingly provides a detailed description of a system for the accounting for and control of nuclear material in an off-load refueled light water moderated power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Periodic inspections of lightning protection systems in intermediate storage facilities of nuclear technological plants

International Nuclear Information System (INIS)

Witzel, Andre; Schulz, Olav

2013-01-01

Especially for nuclear technological plants, periodic inspections of lightning protection systems are of great importance. This article shows the sequence of maintenance programs using the examples of the intermediate storage facilities of the nuclear technological plants Grohnde and Unterweser as well as the central intermediate storage facility in Gorleben and gives a description of the extensive measures of inspecting the external and internal lightning protection and the global earth termination system.

Cold Vacuum Dryer (CVD) Facility Security System Design Description. System 54

International Nuclear Information System (INIS)

WHITEHURST, R.

2000-01-01

This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility security system. The system's primary purpose is to provide reasonable assurance that breaches of security boundaries are detected and assessment information is provided to protective force personnel. In addition, the system is utilized by Operations to support reduced personnel radiation goals and to provide reasonable assurance that only authorized personnel are allowed to enter designated security areas

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Subsurface Facility System Description Document

International Nuclear Information System (INIS)

Eric Loros

2001-01-01

The Subsurface Facility System encompasses the location, arrangement, size, and spacing of the underground openings. This subsurface system includes accesses, alcoves, and drifts. This system provides access to the underground, provides for the emplacement of waste packages, provides openings to allow safe and secure work conditions, and interfaces with the natural barrier. This system includes what is now the Exploratory Studies Facility. The Subsurface Facility System physical location and general arrangement help support the long-term waste isolation objectives of the repository. The Subsurface Facility System locates the repository openings away from main traces of major faults, away from exposure to erosion, above the probable maximum flood elevation, and above the water table. The general arrangement, size, and spacing of the emplacement drifts support disposal of the entire inventory of waste packages based on the emplacement strategy. The Subsurface Facility System provides access ramps to safely facilitate development and emplacement operations. The Subsurface Facility System supports the development and emplacement operations by providing subsurface space for such systems as ventilation, utilities, safety, monitoring, and transportation

Descriptions of selected accidents that have occurred at nuclear reactor facilities

Energy Technology Data Exchange (ETDEWEB)

Bertini, H.W.

1980-04-01

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Descriptions of selected accidents that have occurred at nuclear reactor facilities

International Nuclear Information System (INIS)

Bertini, H.W.

1980-04-01

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established

Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

Energy Technology Data Exchange (ETDEWEB)

SINGH, G.

2000-10-17

This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

Energy Technology Data Exchange (ETDEWEB)

1982-09-01

This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report.

Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

International Nuclear Information System (INIS)

1982-09-01

This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report

Waste isolation facility description: bedded salt

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria. (LK)

Waste isolation facility description: bedded salt

International Nuclear Information System (INIS)

1976-09-01

The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria

Facilities Management Practices in Malaysia: A Literature Review

Directory of Open Access Journals (Sweden)

Isa Nordiana Mohd

2016-01-01

Full Text Available Facilities management in Malaysia has been practiced for decades. The development of its formal practice parallels the improvement of the built environment in the nation. Involvement of the public and private sectors teaming up in arranging the National Asset and Facilities Management (NAFAM in demonstrates the vital collaboration in the facilities management area in Malaysia. Facilities management is seen distinctively as indicated by diverse geographical locations, interests and schools of thought. Facilities management is delegated a service-based industry which gives proficient counsel and administration of clients’ building facilities including residential, commercial, industrial, airports terminals and offices. The aim of this paper is to review the gaps that exist, especially on how FM is being practice in comparison with the published FM body of knowledge. Very relying upon literature, this paper discovered a gap that is an unclear description of current FM applications. This research aims to give new bits of knowledge to upgrade comprehension of FM execution in Malaysia.

Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Retrievable surface storage facility conceptual system design description

Energy Technology Data Exchange (ETDEWEB)

1977-03-01

The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts.

Retrievable surface storage facility conceptual system design description

International Nuclear Information System (INIS)

1977-03-01

The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts

User Delay Cost Model and Facilities Maintenance Cost Model for a Terminal Control Area : Volume 1. Model Formulation and Demonstration

Science.gov (United States)

1978-05-01

The User Delay Cost Model (UDCM) is a Monte Carlo computer simulation of essential aspects of Terminal Control Area (TCA) air traffic movements that would be affected by facility outages. The model can also evaluate delay effects due to other factors...

Heathrow Terminal 5 Excavation Archive (Data Paper

Directory of Open Access Journals (Sweden)

Framework Archaeology

2014-06-01

Full Text Available Framework Archaeology is a Joint Venture agreement between Oxford Archaeology (OA and Wessex Archaeology (WA to provide archaeological services to BAA (formerly British Airports Authority, now Heathrow Airport Holdings Ltd. Given the potential scale of some of BAA's projects, the joint venture enables Framework Archaeology to draw on the full resources of both OA and WA, including site staff, specialist managers, administrative support, and technical facilities. In 1993, BAA plc and Heathrow Airport Limited submitted a joint planning application to develop an additional passenger terminal complex (Terminal 5, together with the provision of aircraft aprons and taxiways, and include the realignment of rivers and landscaping. The resulting archaeological excavations were undertaken as three main phases of work. Excavations in 1996 by the Museum of London Archaeology Service of approximately 4 ha of sludge stockpile areas (site code POK96. Between 1999-2000 Framework Archaeology excavated approximately 21 ha in the Perry Oaks sludge works and adjacent areas (WPR98. Framework Archaeology also undertook excavations between 2002-2007 as part of the construction of Terminal 5 (PSH02, TEC05 covering a further 50 hectares. Importantly the aim of the Terminal 5 archaeological programme was to move beyond the description and recovery of archaeological remains and to arrive at an understanding of the history of human inhabitation and the practical ways in which people established their presence in the material, social and political conditions of their day.

Coal terminal directory

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-06-15

The directory gives a comprehensive listing of the world's coal terminals, in a total of 50 countries including information on throughput, facilities, storage capacity, and vessel size limitation.

Detailed description of an SSAC at the facility level for a low-enriched uranium conversion and fuel fabrication facility

International Nuclear Information System (INIS)

Jones, R.J.

1984-09-01

Some States have expressed a need for more detailed guidance with regard to the technical elements in the design and operation of SSACs for both the national and the international objectives. To meet this need the present document has been prepared, describing the technical elements of an SSAC in considerable detail. The purpose of this document is therefore, to provide a detailed description of a system for the accounting for and control of nuclear material in a model low enriched uranium conversion and fuel fabrication facility which can be used by a facility operator to establish his own system in a way which will provide the necessary information for compliance with a national system for nuclear material accounting and control and for the IAEA to carry out its safeguards responsibilities

Operation and evaluation of the Terminal Configured Vehicle Mission Simulator in an automated terminal area metering and spacing ATC environment

Science.gov (United States)

Houck, J. A.

1980-01-01

This paper describes the work being done at the National Aeronautics and Space Administration's Langley Research Center on the development of a mission simulator for use in the Terminal Configured Vehicle Program. A brief description of the goals and objectives of the Terminal Configured Vehicle Program is presented. A more detailed description of the Mission Simulator, in its present configuration, and its components is provided. Finally, a description of the first research study conducted in the Mission Simulator is presented along with a discussion of some preliminary results from this study.

Description of work for routine groundwater sampling at the Environmental Restoration Disposal Facility

International Nuclear Information System (INIS)

Ford, B.H.

1996-09-01

This document provides a description of work and field implementation guidance for routine (post-baseline) groundwater monitoring sampling program at the Environmental Restoration Disposal Facility. The purpose of this program is to (1) meet the intent of the applicable or relevant and appropriate requirements; (2) document baseline groundwater conditions; (3) monitor those conditions for change; and (4) allow for modifications to groundwater sampling if required by the leachate management program

Siting considerations for LNG import terminals

Energy Technology Data Exchange (ETDEWEB)

Meratla, Z. [CDS Research Ltd., Vancouver, BC (Canada)

2005-07-01

Site selection criteria for liquefied natural gas (LNG) facilities and terminals were reviewed in this PowerPoint presentation. Onshore and offshore sites were discussed. Typical public opposition issues were examined, including public concerns over safety and the environment. Low key consultation processes with local communities was advised to assess levels of interest and opposition during initial stages. It was suggested that desirable LNG sites should not be visible from local communities. Remoteness from built-up areas was advised, as well as ensuring that sites meet the requirements of future expansion and large LNG carriers. Issues concerning waterway drawbacks and exclusion zones were examined, as well as the relative merits of onshore and offshore terminals. It was noted that onshore terminals are accessible to personnel as well as outside emergency response resources, and are less susceptible to weather related downtime. In addition, onshore spills are generally impounded. Offshore LNG import terminals are visible from shorelines and susceptible to stray marine traffic and abnormal events. Siting considerations for offshore facilities include sensitive areas; shipping channels; foundation issues; shipping lane access; and offshore pipeline lengths. Issues concerning loading arms, remote flare systems, integral ballast and process equipment for offshore facilities were discussed. Membrane type storage systems and tank construction details were presented as well as details of self supporting storage systems. A comparison of gravity-based structures and floating facilities was presented. It was concluded that floating LNG facilities have well developed security procedures, passive protection and automatic intruder detection alarms. tabs., figs.

33 CFR 105.290 - Additional requirements-cruise ship terminals.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Additional requirements-cruise ship terminals. 105.290 Section 105.290 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY MARITIME SECURITY MARITIME SECURITY: FACILITIES Facility Security Requirements § 105.290 Additional requirements—cruise ship terminals...

Description of pelletizing facility

Energy Technology Data Exchange (ETDEWEB)

Vojin Cokorilo; Dinko Knezevic; Vladimir Milisavljevic [University of Belgrade, Belgrade (Serbia). Faculty of Mining and Geology

2006-07-01

A lot of electrical energy in Serbia was used for heating, mainly for domestics. As it is the most expensive source for heating the government announced a National Program of Energy Efficiency with only one aim, to reduce the consumption of electric energy for the heating. One of the contributions to mentioned reduction is production of coal pellets from the fine coal and its use for domestic heating but also for heating of schools, hospitals, military barracks etc. Annual production of fine coal in Serbia is 300,000 tons. The stacks of fine coal present difficulties at each deep mine because of environmental pollution, spontaneous combustion, low price, smaller market etc. To overcome the difficulties and to give the contribution to National Program of Energy Efficiency researchers from the Department of Mining Engineering, the University of Belgrade designed and realized the project of fine coal pelletizing. This paper describes technical aspect of this project. Using a CPM machine Model 7900, a laboratory facility, then a semi-industrial pelletizing facility followed by an industrial facility was set up and produced good quality pellets. The plant comprised a coal fines hopper, conveyor belt, hopper for screw conveyor, screw conveyor, continuous mixer conditioner, binder reservoir, pump and pipelines, pellet mill, product conveyor belt and product hopper. 4 refs., 3 figs., 1 tab.

ATLAS Facility Description Report

International Nuclear Information System (INIS)

Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik; Cho, Seok; Choi, Ki Yong

2009-04-01

A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS has the same two-loop features as the APR1400 and is designed according to the well-known scaling method suggested by Ishii and Kataoka to simulate the various test scenarios as realistically as possible. It is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating loop-type. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations in detail

Descriptions of representative contaminated sites and facilities within the DOE complex

International Nuclear Information System (INIS)

Short, S.M.; Buck, J.W.; Clark, L.L.; Fletcher, J.F.; Glantz, C.S.; Holdren, G.R.; Huesties, L.R.; Williams, M.D.; Oates, L.

1994-10-01

The U.S. Department of Energy (DOE) has initiated efforts to prepare a Programmatic Environmental Impact Statement (PEIS) that will analyze the existing environmental restoration and waste management program and evaluate alternatives for an integrated program. The alternatives being evaluated include (1) a open-quotes No Actionclose quotes alternative as required by the National Environmental Policy Act (NEPA), (2) an Applicable, Relevant, and Appropriate Requirements (ARAR)-driven alternative, (3) a land-use-driven alternative, (4) a health-risk-driven alternative, and (5) a combination land-use and health-risk-driven alternative. The analytical approach being taken to evaluate each of these alternatives is to perform a remedial engineering analysis and human health and ecosystem effects analyses on every contaminated site and facility in the DOE complex. One of Pacific Northwest Laboratory's (PNL) roles in this approach has been to compile the source term and environmental setting data needed to drive each of these analyses. To date, over 10,000 individual contaminated sites and facilities located throughout the DOE complex of installations have been identified and at least some minimal data compiled on each. The PEIS analyses have been appreciably simplified by categorizing all of these contaminated sites and facilities into six broad categories: (1) contaminated buildings, (2) contaminated soils, (3) solid waste sites (e.g., burial grounds), (4) liquid containment structures (e.g., tanks), (5) surface water sites, and (6) contaminated groundwater sites. A report containing a complete description of each of these thousands of contaminated sites and facilities would be tremendously large and unwildy, as would separate reports describing the application of the analytical methodologies to each

12 CFR 725.6 - Termination of membership.

Science.gov (United States)

2010-01-01

... CREDIT UNION ADMINISTRATION CENTRAL LIQUIDITY FACILITY § 725.6 Termination of membership. (a) A member of... member has failed to comply with any provision of the National Credit Union Central Liquidity Facility...

SIRKULASI TERMINAL PENUMPANG KAPAL LAUT

Directory of Open Access Journals (Sweden)

Etsa Purnama Sari

2014-01-01

transportation demand is quite high in public as well as a major proponent of development of social, cultural, and economy. Thus, to support this means of transportation, facility in form of port is needed. A port must have some basic and support facilities, which includes ship passenger terminal to accommodate arrival of departure of passengers. Problems which usually occur in ship passenger terminal caused by poor planning of circulation are: discomfort in activities, long distance of circulations which connect one activity to another, disorganized embarkation and disembarkation, and confusing distribution of passengers and passenger’s comperes’ pathways. From those conditions, sometimes it gives opportunity for ticket brokers and passengers without tickets who could board ships without proper requirements. A proper planning of circulation requires analysis of elements of circulation which includes entrance, circulation pattern, circulation path, and form of circulation space. Furthermore, such elements were studied through problem seeking, then descriptively analyze through research’s object depiction from Yokohama International Passenger Terminal, Kobe Port Terminal, and Osanbashi Hall Passenger Terminal REFERENCES __. 1996. Peraturan Pemerintah RI No. 70 Tahun 1996 tentang Kepelabuhan, Departemen Perhubungan RI Alucci, Marcia Peinando; Leonardo Marques Monteiro. 2009. Thermal Comfort Index for The Assessment of Outdoor Urban Spaces in Subtropical Climates. University of Sao Paulo. Sao Paulo Andiani, Dita. 2011. Terminal Feri Domestik Sekupang – Batam (Arsitektur Simbolis. Laporan Perancangan Tugas Akhir Departemen Arsitektur, Universitas Sumatera Utara. Diunduh dari http://repository.usu.ac.id/ handle/123456789/26972 Ching, Francis D. K. 2000. Arsitektur Bentuk, Ruang, dan Tatanan; edisi kedua. Erlangga. Jakarta Cyril, Haris 1975. Dictionary of Architecture And  Construction. McGraw-Hill Professional. New York. Haronjeff, Robert. 1993. Perencanaan dan Perancangan

Descriptions of reference LWR facilities for analysis of nuclear fuel cycles

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Kabele, T.J.

1979-09-01

To contribute to the Department of Energy's identification of needs for improved environmental controls in nuclear fuel cycles, a study was made of a light water reactor system. A reference LWR fuel cycle was defined, and each step in this cycle was characterized by facility description and mainline and effluent treatment process performance. The reference fuel cycle uses fresh uranium in light water reactors. Final treatment and ultimate disposition of waste from the fuel cycle steps were not included, and the waste is assumed to be disposed of by approved but currently undefined means. The characterization of the reference fuel cycle system is intended as basic information for further evaluation of alternative effluent control systems.

Descriptions of reference LWR facilities for analysis of nuclear fuel cycles

International Nuclear Information System (INIS)

Schneider, K.J.; Kabele, T.J.

1979-09-01

To contribute to the Department of Energy's identification of needs for improved environmental controls in nuclear fuel cycles, a study was made of a light water reactor system. A reference LWR fuel cycle was defined, and each step in this cycle was characterized by facility description and mainline and effluent treatment process performance. The reference fuel cycle uses fresh uranium in light water reactors. Final treatment and ultimate disposition of waste from the fuel cycle steps were not included, and the waste is assumed to be disposed of by approved but currently undefined means. The characterization of the reference fuel cycle system is intended as basic information for further evaluation of alternative effluent control systems

29 CFR 1917.17 - Railroad facilities.

Science.gov (United States)

2010-07-01

... 29 Labor 7 2010-07-01 2010-07-01 false Railroad facilities. 1917.17 Section 1917.17 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) MARINE TERMINALS Marine Terminal Operations § 1917.17 Railroad facilities. (a) Work shall be...

High Exposure Facility Technical Description

Energy Technology Data Exchange (ETDEWEB)

Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

2008-02-12

The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

Energy Technology Data Exchange (ETDEWEB)

Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

2010-04-28

The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary

International Nuclear Information System (INIS)

Lauridsen, Kurt

2001-02-01

The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

Fault detection and protection system for neutral beam generators on the Neutral Beam Engineering Test Facility (NBETF)

International Nuclear Information System (INIS)

deVries, G.J.; Chesley, K.L.; Owren, H.M.

1983-12-01

Neutral beam sources, their power supplies and instrumentation can be damaged from high voltage sparkdown or from overheating due to excessive currents. The Neutral Beam Engineering Test Facility (NBETF) in Berkeley has protective electronic hardware that senses a condition outside a safe operating range and generates a response to terminate such a fault condition. A description of this system is presented in this paper. 8 references, 2 figures, 2 tables

JCO criticality accident termination operation

OpenAIRE

金盛 正至

2010-01-01

In 2001, we summarized the circumstances surrounding termination of the JCO criticality accident based on testimony in the Mito District Court on December 17, 2001. JCO was the company for uranium fuels production in Japan. That document was assembled based on actual testimony in the belief that a description of the work involved in termination of the accident would be useful in some way for preventing nuclear disasters in the future. This year is the tenth year of the JCO criticality acciden...

Material control in nuclear fuel fabrication facilities. Part I. Fuel descriptions and fabrication processes, P.O. 1236909 Final report

International Nuclear Information System (INIS)

Borgonovi, G.M.; McCartin, T.J.; Miller, C.L.

1978-12-01

The report presents information on foreign nuclear fuel fabrication facilities. Fuel descriptions and fuel fabrication information for three basic reactor types are presented: The information presented for LWRs assumes that Pu--U Mixed Oxide Fuel (MOX) will be used as fuel

Development of BWR [boiling water reactor] and PWR [pressurized water reactor] event descriptions for nuclear facility simulator training

International Nuclear Information System (INIS)

Carter, R.J.; Bovell, C.R.

1987-01-01

A number of tools that can aid nuclear facility training developers in designing realistic simulator scenarios have been developed. This paper describes each of the tools, i.e., event lists, events-by-competencies matrices, and event descriptions, and illustrates how the tools can be used to construct scenarios

Knowledge of Dementia: Do family members understand dementia as a terminal condition?

Science.gov (United States)

Andrews, Sharon; McInerney, Fran; Toye, Christine; Parkinson, Camillus-Anthony; Robinson, Andrew

2017-07-01

Current research identifies advanced dementia to be the terminal phase of this progressive and incurable condition. However, there has been relatively little investigation into how family members of people with advanced dementia understand their relative's condition. In this article, we report on semi-structured interviews with 10 family members of people with advanced dementia, in a residential aged care facility. Using a qualitative, descriptive design, we explored family members' understandings of dementia, whether they were aware that it was a terminal condition, and the ways they developed their understandings. Findings revealed that the majority of family members could not recognize the terminal nature of dementia. Relying on predominantly lay understandings, they had little access to formal information and most failed to conceptualize a connection between dementia and death. Moreover, family members engaged in limited dialogue with aged care staff about such issues, despite their relatives being in an advanced stage of the disease. Findings from our study suggest that how family members understand their relative's condition requires greater attention. The development of staff/family partnerships that promote shared communication about dementia and dying may enhance family members' understandings of the dementia trajectory and the types of decisions they may be faced with during the more advanced stages of the disease.

Zinc-enriched (ZEN) terminals in mouse spinal cord

DEFF Research Database (Denmark)

Jo, S M; Danscher, G; Schrøder, H D

2000-01-01

The general distribution of zinc-enriched (ZEN) terminals in mouse spinal cord was investigated at light microscopic level by means of zinc transporter-3 immunohistochemistry (ZnT3(IHC)) and zinc selenium autometallography (ZnSe(AMG)). Staining for ZnT3(IHC) corresponded closely to the Zn...... dendrites. These ZEN terminals in the ventral horn were in general larger than those in the dorsal horn. This is the first description of the pattern of ZEN terminals in mouse spinal cord....

Cold Vacuum Drying (CVD) Facility Vacuum Purge System Chilled Water System Design Description. System 47-4

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This system design description (SDD) addresses the Vacuum Purge System Chilled Water (VPSCHW) system. The discussion that follows is limited to the VPSCHW system and its interfaces with associated systems. The reader's attention is directed to Drawings H-1-82162, Cold Vacuum Drying Facility Process Equipment Skid PandID Vacuum System, and H-1-82224, Cold Vacuum Drying Facility Mechanical Utilities Process Chilled Water PandID. Figure 1-1 shows the location and equipment arrangement for the VPSCHW system. The VPSCHW system provides chilled water to the Vacuum Purge System (VPS). The chilled water provides the ability to condense water from the multi-canister overpack (MCO) outlet gases during the MCO vacuum and purge cycles. By condensing water from the MCO purge gas, the VPS can assist in drying the contents of the MCO

ATLAS Facility and Instrumentation Description Report

International Nuclear Information System (INIS)

Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik

2009-06-01

A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating looptype. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations which are specific to the simulation of 50% DVI line break accident of the APR1400 for supporting the 50 th OECD/NEA International Standard Problem Exercise (ISP-50)

User Delay Cost Model and Facilities Maintenance Cost Model for a Terminal Control Area : Volume 2. User's Manual and Program Documentation for the User Delay Cost Model

Science.gov (United States)

1978-05-01

The User Delay Cost Model (UDCM) is a Monte Carlo simulation of certain classes of movement of air traffic in the Boston Terminal Control Area (TCA). It incorporates a weather module, an aircraft generation module, a facilities module, and an air con...

Berkeley Nuclear Laboratories Reactor Physics Mk. III Experimental Programme. Description of facility and programme for 1971

Energy Technology Data Exchange (ETDEWEB)

Nunn, R M; Waterson, R H; Young, J D

1971-01-15

Reactor physics experiments have been carried out at Berkeley Nuclear Laboratories during the past few years in support of the Civil Advanced Gas-Cooled Reactors (Mk. II) the Generating Board is building. These experiments are part of an overall programme whose objective is to assess the accuracy of the calculational methods used in the design and operation of these reactors. This report provides a description of the facility for the Mk. III experimental programme and the planned programme for 1971.

Concept Layout Model of Transportation Terminals

Directory of Open Access Journals (Sweden)

Li-ya Yao

2012-01-01

Full Text Available Transportation terminal is the key node in transport systems. Efficient terminals can improve operation of passenger transportation networks, adjust the layout of public transportation networks, provide a passenger guidance system, and regulate the development of commercial forms, as well as optimize the assembly and distribution of modern logistic modes, among others. This study aims to clarify the relationship between the function and the structure of transportation terminals and establish the function layout design. The mapping mechanism of demand, function, and structure was analyzed, and a quantitative relationship between function and structure was obtained from a design perspective. Passenger demand and terminal structure were decomposed into several demand units and structural elements following the principle of reverse engineering. The relationship maps between these two kinds of elements were then analyzed. Function-oriented concept layout model of transportation terminals was established using the previous method. Thus, a technique in planning and design of transportation structures was proposed. Meaningful results were obtained from the optimization of transportation terminal facilities, which guide the design of the functional layout of transportation terminals and improve the development of urban passenger transportation systems.

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

1995 Baseline solid waste management system description

International Nuclear Information System (INIS)

Anderson, G.S.; Konynenbelt, H.S.

1995-09-01

This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

Generic description of facilities at the shaft head (auxiliary entrance installations) of deep geological repositories

International Nuclear Information System (INIS)

2016-10-01

In a deep geological repository, the access structures function as the link between the surface and the installations and structures at the disposal level. In the planned implementation scenarios, at least two access structures will be in operation up to the time of closure of the repository. The radioactive waste will be transported via the main access from the surface to the disposal level during emplacement operations. For the construction and operation of a deep geological repository, additional access structures are required. These auxiliary accesses and the associated surface infrastructure (e.g. shaft head installations) form the subject of this report. To provide as broad and comprehensive a description as possible, seven types of auxiliary access facilities are defined; these are characterised in line with the current status of planning and their functions and impacts are described. During construction, operation and dismantling of auxiliary access facilities, the usual conventional safety measures (inter alia) have to be observed (e.g. groundwater protection, fire prevention, facility security, accident prevention). Regarding the 'Ordinance on Protection against Major Accidents' no large quantities of hazardous materials, i.e. above the corresponding threshold quantities, are to be expected in the auxiliary access facilities. Proper handling and compliance with applicable regulations in all phases will ensure no hazard to humans and the environment. As no handling of radioactive materials is foreseen in the auxiliary access facilities, and because exhaust air and waste water from the controlled zones of a repository will, in principle, be removed via the main access and not the auxiliary accesses, a safety-relevant emission of radioactive substances and transport of contaminated material can be ruled out for the auxiliary access facilities during both normal operation and also in the case of an accident. Based on the information presented in

The transportation operations system: A description

International Nuclear Information System (INIS)

Best, R.E.; Danese, F.L.; Dixon, L.D.; Peterson, R.W.; Pope, R.B.

1990-01-01

This paper presents a description of the system for transporting radioactive waste that may be deployed to accomplish the assigned system mission, which includes accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from waste generator sites and transporting them to the FWMS destination facilities. The system description presented here contains, in part, irradiated fuel and waste casks, ancillary equipments, truck, rail, and barge transporters, cask and vehicle traffic management organizations, maintenance facilities, and other operations elements. The description is for a fully implemented system, which is not expected to be achieved, however, until several years after initial operations. 6 figs

JCO criticality accident termination operation

International Nuclear Information System (INIS)

Kanamori, Masashi

2010-07-01

In 2001, we summarized the circumstances surrounding termination of the JCO criticality accident based on testimony in the Mito District Court on December 17, 2001. JCO was the company for uranium fuels production in Japan. That document was assembled based on actual testimony in the belief that a description of the work involved in termination of the accident would be useful in some way for preventing nuclear disasters in the future. The description focuses on the witness' own behavior, and what he saw and heard, and thus is written from the perspective of action by one individual. This was done simply because it was easier for the witness to write down his memories as he remembers them. Description of the activities of other organizations and people is provided only as necessary, to ensure that consistency in the descriptive approach is not lost. The essentials of this report were rewritten as a third-person objective description in the summary of the report by the Atomic Energy Society of Japan (AESJ). Since then, comments have been received from sources such as former members of the Nuclear Safety Commission (Dr. Kenji Sumita and Dr. Akira Kanagawa), concerned parties from the former Science and Technology Agency, and reports from the JCO Criticality Accident Investigation Committee of the AESJ, and thus this report was rewritten to correct incorrect information, and add material where that was felt to be necessary. This year is the tenth year of the JCO criticality accident. To mark this occasion we have decided to translate the record of what occurred at the accident site into English so that more people can draw lessons from this accident. This report is an English version of JAEA-Technology 2009-073. (author)

Summary description of the Fast Flux Test Facility

International Nuclear Information System (INIS)

Cabell, C.P.

1980-12-01

This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like

Over facility design description for the CPDF [Centrifuge Plant Demonstration Facility]: SDD-1 [System Design Description

International Nuclear Information System (INIS)

1987-04-01

The Centrifuge Plant Demonstration Facility (CPDF) is an essential part of the continuing development of first-production-plant centrifuge technology that will integrate centrifuge machines into a process and enrichment plant design. The CPDF will provide facilities for testing and continued development of a unit cascade in direct support of the commercial Gas Centrifuge Enrichment Plant (GCEP). The basic cascade-oriented equipment, feed, withdrawal, drive system, process piping, utility piping, and other auxiliary and support equipment will be tested in an operating configuration that represents, to the extent possible, GCEP arrangement and operating conditions. The objective will be to demonstrate procedures for production cascade installation, start-up, operation, and maintenance, and to provide proof of overall cascade and associated system design, construction, and operating and maintenance concepts. To the maximum possible extent, all equipment for the CPDF will be procured from commercial sources. Centrifuges will be procured from industry using government-supplied specifications and drawings. The existing Component Preparation Laboratory (CPL) located near the CPDF site will be used for centrifuge component receiving, inspection, assembly, and qualification testing of pre-production test machines. Later in the test program, samples of production machines planned for use in the GCEP will be tested in the CPDF

Predictable uncertainty about terminal operations in the sea

Directory of Open Access Journals (Sweden)

S. Hess

2010-06-01

Full Text Available This paper considers a problem of planning short term operations in a bulk terminal faced by port management when making tactical decisions. Ship loading and discharging, cargo stocking, the maintenance and service of facility equipment are regular operations of a bulk terminal which is a subsystem of a sea port the conduct of which is subject to difficult-to-predict or unforeseen influences. The problem that port management encounters in day to day operations looks into making the best possible plan with the scheduled duration of operations/states and transition instants, considering various internal and external factors influencing terminal performance. A state and transition model is used for deriving effective solutions to obtaining the state order and state transition time of a bulk terminal with an objective of minimizing operational costs. The behaviour of the terminal is tested applying the stochastic and deterministic method.

International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

International Nuclear Information System (INIS)

2006-12-01

The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-12-15

The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

Distriubted terminal support in a data acquisition system for nuclear research reactors

International Nuclear Information System (INIS)

Shah, R.R.; Capel, A.C.; Pensom, C.F.

1980-01-01

A comprehensive and flexible terminal support facility is being designed to provide the necessary interactive man-machine interface for REDNET, a distriubted data aquisition system for nuclear research reactors. Host processors and a large number of terminals are linked via three physically independent but interconnected terminal support subsystems, which use in-house developed equipment based on cable TV technology. The CCITT X-25 protocol is supported, and virtual circuits are used for communications between terminals and software functions in host processors. This paper presents the requirements and conceptual design of the major terminal support components. (auth)

Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

International Nuclear Information System (INIS)

Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

1993-01-01

This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

75 FR 18572 - Facility Control Numbers

Science.gov (United States)

2010-04-12

...), biodiesel production facilities (BCN), or ethanol production facilities (ECN). A taxable fuel registrant... -CB-) will be issued a BCN for each biodiesel production physical location that a registrant in good... approved terminal. Each TCN identifies a unique physical location in the bulk transport/delivery system and...

Reliability and safety program plan outline for the operational phase of a waste isolation facility

International Nuclear Information System (INIS)

Ammer, H.G.; Wood, D.E.

1977-01-01

A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

1994-11-01

The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

29 CFR 1917.26 - First aid and lifesaving facilities.

Science.gov (United States)

2010-07-01

... 29 Labor 7 2010-07-01 2010-07-01 false First aid and lifesaving facilities. 1917.26 Section 1917..., DEPARTMENT OF LABOR (CONTINUED) MARINE TERMINALS Marine Terminal Operations § 1917.26 First aid and..., to the employer. (b) A first aid kit shall be available at the terminal, and at least one person...

Hanford Facility contingency plan

International Nuclear Information System (INIS)

Sutton, L.N.; Miskho, A.G.; Brunke, R.C.

1993-10-01

The Hanford Facility Contingency Plan, together with each TSD unit-specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. This plan includes descriptions of responses to a nonradiological hazardous materials spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. This plan includes descriptions of responses for spills or releases as a result of transportation activities, movement of materials, packaging, and storage of hazardous materials

LAMPF: a nuclear research facility

International Nuclear Information System (INIS)

Livingston, M.S.

1977-09-01

A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

48 CFR 215.404-71-4 - Facilities capital employed.

Science.gov (United States)

2010-10-01

... encouraging and rewarding capital investment in facilities that benefit DoD. It recognizes both the facilities... anticipated industrial base enhancing benefits resulting from the facilities capital investment, including— (A... investment recovery, such as termination protection clauses and capital investment indemnification. (2) Above...

A Dry-Slip Facility for Fish Terminals on Open Coasts

DEFF Research Database (Denmark)

Burcharth, Hans F.; Schmidt, Jens- Chr.; Odoom, Daniel Semanu

The paper describes a low cost facility for landing and shipping of fish and for bringing fishing boats ashore in periods of bad weather. The facility is meant for open coasts and represents an improvement from beach landing. Being a wooden pile structure it is much cheaper to construct than conv...

Overview of the National Waste Terminal Storage Program

International Nuclear Information System (INIS)

Zerby, C.D.

1976-01-01

The following seven distinct steps necessary for developing a terminal storage facility are discussed: identification of formations of interest; reconnaissance surveys; in situ tests; area studies; detailed confirmation studies; pilot plant operations; and conversion of the pilot plant into a federal repository

47 CFR 68.110 - Compatibility of the public switched telephone network and terminal equipment.

Science.gov (United States)

2010-10-01

... changes in its communications facilities, equipment, operations or procedures, where such action is... in this part. If such changes can be reasonably expected to render any customer's terminal equipment... network and terminal equipment. 68.110 Section 68.110 Telecommunication FEDERAL COMMUNICATIONS COMMISSION...

Misoprostol alone for the termination of Pregnancy

African Journals Online (AJOL)

The use of Misoprostol for ter- mination of pregnancy has been approved by the Medicines Control. Council of South Africa. It is part of the approved protocol for termina- tion of pregnancy in public sector facilities in the Western Cape.1. Reference. 1. Provincial Administration: Western Cape: Termination of Pregnancy (Top):.

The exploratory studies facility (ESF) at Yucca Mountain - Description and status

International Nuclear Information System (INIS)

Simecka, W.B.; Replogle, J.M.; Mckenzie, D.G.

1994-01-01

The Exploratory Studies Facility (ESF) at Yucca Mountain, Nevada will be a 25 kilometer underground network of inclined ramps, tunnels, and test alcoves. It will serve as an underground laboratory for the execution of a testing program conceived to assess the suitability of Yucca Mountain as a site to host a potential high level nuclear waste repository. This paper contains a description of the ESF, a summary of the major types of tests currently planned, and a report on the current status of the ongoing design and construction activities. The ESF is being designed and constructed in phases. Currently, the Detailed Design, or open-quotes Title II Designclose quotes is centered on the second of ten major design packages. Construction has begun on excavation of the open-quotes starter tunnelclose quotes for a Tunnel Boring Machine (TBM) expected to begin operation in late FY 1994. The EFS program will provide information critical to the evaluation of Yucca Mountain as a potential repository site, and will house a suite of state-of-the-art tests designed to gather this information. The ESF is a one of a kind opportunity to examine, in minute detail, all facets of a sites' geology; its thermal, mechanical, and hydrologic properties; and to study the linkages between these properties

Descriptions of reference LWR facilities for analysis of nuclear fuel cycles. Appendixes

International Nuclear Information System (INIS)

Schneider, K.J.; Kabele, T.J.

1979-09-01

The appendixes present the calculations that were used to derive the release factors discussed for each fuel cycle facility in Volume I. Appendix A presents release factor calculations for a surface mine, underground mine, milling facility, conversion facility, diffusion enrichment facility, fuel fabrication facility, PWR, BWR, and reprocessing facility. Appendix B contains additional release factors calculated for a BWR, PWR, and a reprocessing facility. Appendix C presents release factors for a UO 2 fuel fabrication facility

Requirements of on-site facilities

International Nuclear Information System (INIS)

Burchardt, H.

1977-01-01

1) Requirements of on-site facilities: a) brief description of supplying the site with electricity and water; communication facilities, b) necessary facilities for containment and pipeline installation, c) necessary facilities for storage, safety, accommodation of personnel, housing; workshops; 2) Site management: a) Organisation schedules for 'turn-key-jobs' and 'single commission', b) Duties of the supervisory staff. (orig.) [de

Assessing Port Governance, Devolution and Terminal Performance in Nigeria

Directory of Open Access Journals (Sweden)

D. E. Onwuegbuchunam

2018-02-01

Full Text Available Concerns about performance and efficiency in port terminals led many national governments to embark on port reforms. The Federal government of Nigeria, for example, adopted the Landlord port model which brought about concessioning of port terminals to private operators. Despite high investments in terminal facilities by the private terminal operators, there are still complaints about level of service offered to port users. This paper applied key performance indicator metrics and parameters of queuing model in assessing performance of Nigeria’s concessioned port terminals. Data for the study were obtained from terminal level records of cargo and ship handling activities for years 2000 to 2015. Major findings indicate that cargo and vessel throughputs improved after the reforms in the six ports examined. However, much variability was observed in trends in ships’ turnround times across all ports after the concession policy implementation. Additional results from the queuing model analysis suggest that the high ships turnround times observed in some ports are associated to delays in ship operation at the berths. The paper recommends that policy interventions be focused on ship operations at the berths as a step in improving service level in the port terminals.

29 CFR 1910.16 - Longshoring and marine terminals.

Science.gov (United States)

2010-07-01

...) Commercial diving operations. Subpart T; (iii) Electrical. Subpart S when shore-based electrical... sulfide, § 1910.1000 (See § 1918.94 (f)). (x) Powered industrial truck operator training, Subpart N... facilities contiguous to electrical power generating plants. (2) Part 1910 does not apply to marine terminals...

Analyzing Program Termination and Complexity Automatically with AProVE

DEFF Research Database (Denmark)

Giesl, Jürgen; Aschermann, Cornelius; Brockschmidt, Marc

2017-01-01

In this system description, we present the tool AProVE for automatic termination and complexity proofs of Java, C, Haskell, Prolog, and rewrite systems. In addition to classical term rewrite systems (TRSs), AProVE also supports rewrite systems containing built-in integers (int-TRSs). To analyze...... programs in high-level languages, AProVE automatically converts them to (int-)TRSs. Then, a wide range of techniques is employed to prove termination and to infer complexity bounds for the resulting rewrite systems. The generated proofs can be exported to check their correctness using automatic certifiers...

Thermionic system evaluated test (TSET) facility description

Science.gov (United States)

Fairchild, Jerry F.; Koonmen, James P.; Thome, Frank V.

1992-01-01

A consortium of US agencies are involved in the Thermionic System Evaluation Test (TSET) which is being supported by the Strategic Defense Initiative Organization (SDIO). The project is a ground test of an unfueled Soviet TOPAZ-II in-core thermionic space reactor powered by electrical heat. It is part of the United States' national thermionic space nuclear power program. It will be tested in Albuquerque, New Mexico at the New Mexico Engineering Research Institute complex by the Phillips Laboratoty, Sandia National Laboratories, Los Alamos National Laboratory, and the University of New Mexico. One of TSET's many objectives is to demonstrate that the US can operate and test a complete space nuclear power system, in the electrical heater configuration, at a low cost. Great efforts have been made to help reduce facility costs during the first phase of this project. These costs include structural, mechanical, and electrical modifications to the existing facility as well as the installation of additional emergency systems to mitigate the effects of utility power losses and alkali metal fires.

Cold Vacuum Drying facility effluent drain system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) effluent drain system (EFS). The primary function of the EFS is to collect and transport fire suppression water discharged into a CVDF process bay to a retention basin located outside the facility. The EFS also provides confinement of spills that occur inside a process bay and allows non-contaminated water that drains to the process bay sumps to be collected until sampling and analysis are complete

Cold Vacuum Drying facility deionized water system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) de-ionized water system. The de-ionized water system is used to provide clean, conditioned water, free from contaminants, chlorides and iron for the CVD Facility. Potable water is supplied to the deionized water system, isolated by a backflow prevention device. After the de-ionization process is complete, via a packaged de-ionization unit, de-ionized water is supplied to the process deionization unit

Mound facility physical characterization

Energy Technology Data Exchange (ETDEWEB)

Tonne, W.R.; Alexander, B.M.; Cage, M.R.; Hase, E.H.; Schmidt, M.J.; Schneider, J.E.; Slusher, W.; Todd, J.E.

1993-12-01

The purpose of this report is to provide a baseline physical characterization of Mound`s facilities as of September 1993. The baseline characterizations are to be used in the development of long-term future use strategy development for the Mound site. This document describes the current missions and alternative future use scenarios for each building. Current mission descriptions cover facility capabilities, physical resources required to support operations, current safety envelope and current status of facilities. Future use scenarios identify potential alternative future uses, facility modifications required for likely use, facility modifications of other uses, changes to safety envelope for the likely use, cleanup criteria for each future use scenario, and disposition of surplus equipment. This Introductory Chapter includes an Executive Summary that contains narrative on the Functional Unit Material Condition, Current Facility Status, Listing of Buildings, Space Plans, Summary of Maintenance Program and Repair Backlog, Environmental Restoration, and Decontamination and Decommissioning Programs. Under Section B, Site Description, is a brief listing of the Site PS Development, as well as Current Utility Sources. Section C contains Site Assumptions. A Maintenance Program Overview, as well as Current Deficiencies, is contained within the Maintenance Program Chapter.

Canwest propane: Canwest Propane's newest terminal delivers the winning conditions for B.C. market expansion

International Nuclear Information System (INIS)

Anon

2004-01-01

Opening of a new propane terminal in Surrey, BC by Canwest Propane Ltd., is reported. The facility is the first rail terminal opened by Canwest, and is intended to serve the greater Vancouver area, Vancouver island and the US Northwest, specifically Washington State. The Surrey location allows the company to service its business by rail, the most efficient method of getting product to the Lower Mainland. The facility sits on 4.5 acres of land; a CN rail track runs alongside the site, where six 30,000 gallon storage tanks are located. About 60 million litres of propane is expected to be distributed from the terminal, with further expansion anticipated both on Vancouver Island and in the US Northwest. photos

Outline of a fuel treatment facility in NUCEF

International Nuclear Information System (INIS)

Sugikawa, Susumu; Umeda, Miki; Kokusen, Junya

1997-03-01

This report presents outline of the nuclear fuel treatment facility for the purpose of preparing solution fuel used in Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF), including descriptions of process conditions and dimensions of major process equipments on dissolution system of oxide fuel, chemical adjustment system, purification system, acid recovery system, solution fuel storage system, and descriptions of safety design philosophy such as safety considerations of criticality, solvent fire, explosion of hydrogen and red-oil and so on. (author)

SURF II: Characteristics, facilities, and plans

International Nuclear Information System (INIS)

Madden, R.P.; Canfield, R.; Furst, M.; Hamilton, A.; Hughey, L.

1992-01-01

This facility report describes the Synchrotron Ultraviolet Radiation Facility (SURF II) operated by the National Institute of Standards and Technology, Gaithersburg, Maryland. SURF II is a 300-MeV electron storage ring which provides well characterized continuum radiation from the far infrared to the soft x-ray region with the critical wavelength at 17.4 nm. Brief descriptions are given of the user facilities, the characteristics of the synchrotron radiation, the main storage ring, the injector system and each of the operating beam lines, and associated instruments. Further description is given of expansion plans for additional beam lines

Waste isolation facility description for the spent fuel cycle, bedded salt

International Nuclear Information System (INIS)

1977-05-01

Details are given on surface facilities, shafts and hoists, mine facilities, ventilation systems, land improvements, and utilities. Accidents, confinement, and safety criteria are covered. Appendices are provided on mine layout and development, mine operations, shaft construction information, and analysis concerning canister rupture inside the proposed waste isolation facility

Planning of Terminal Construction at the Port of Ploce

Directory of Open Access Journals (Sweden)

Čedomir Dundović

2007-07-01

Full Text Available The paper presents a systematic and comprehensive analysisof both the technological justification for the constructionof a container/multi-purpose terminal and a dry bulk terminal,and the efficiency of loading/unloading facilities. The organisationof Croatian ports is inefficient and the technology usedin outdated. Traffic links with the mainland, the continent andthe world are unsatisfactory, with traffic infrastructure impactingadversely on operational efficiency. Analysis results of thepresent condition of port traffic and the influence of traffic onport operations and development indicate that the Port ofPlace lacks a multi-purpose terminal that would enable modemcontainer traffic. Because of the inefficient cargo-handlingprocedure and manner of storing bulk cargo in the Port ofPlace, it is necessary to plan the construction of a coal andiron ore terminal taking into account spatia~ technological,economic and ecological development factors. The authorsalso examine the importance of regional initiatives spurringthe development of Croatia and, in particular, the port systemas part of the EU's Pan-European transport corridor V BranchC. Research results are presented by a traffic and technologicaldesign for a container/multi-purpose terminal and dry bulkterminal capable of providing an appropriate level of servicefor all terminal users.

TMACS I/O termination point listing. Revision 1

International Nuclear Information System (INIS)

Scaief, C.C. III.

1994-01-01

This document provides a listing of all analog and discrete input/output (I/O) points connected to the Tank Monitor and Control System (TMACS). The list also provides other information such as the point tag name, termination location, description, drawing references and other parameters. The purpose is to define each point's unique tag name and to cross reference the point with other associated information that may be necessary for activities such as maintenance, calibration, diagnostics, or design changes. It provides a list in one document of all I/O points that would otherwise only be available by referring to all I/O termination drawings

TMACS I/O termination point listing. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Scaief, C.C. III

1994-09-13

This document provides a listing of all analog and discrete input/output (I/O) points connected to the Tank Monitor and Control System (TMACS). The list also provides other information such as the point tag name, termination location, description, drawing references and other parameters. The purpose is to define each point`s unique tag name and to cross reference the point with other associated information that may be necessary for activities such as maintenance, calibration, diagnostics, or design changes. It provides a list in one document of all I/O points that would otherwise only be available by referring to all I/O termination drawings.

Data communication between data terminal equipment and the JPL administrative data base management system

Science.gov (United States)

Iverson, R. W.

1984-01-01

Approaches to enabling an installed base of mixed data terminal equipment to access a data base management system designed to work with a specific terminal are discussed. The approach taken by the Jet Propulsion Laboratory is described. Background information on the Jet Propulsion Laboratory (JPL), its organization and a description of the Administrative Data Base Management System is included.

Synchrotron radiation facilities

CERN Multimedia

1972-01-01

Particularly in the past few years, interest in using the synchrotron radiation emanating from high energy, circular electron machines has grown considerably. In our February issue we included an article on the synchrotron radiation facility at Frascati. This month we are spreading the net wider — saying something about the properties of the radiation, listing the centres where synchrotron radiation facilities exist, adding a brief description of three of them and mentioning areas of physics in which the facilities are used.

Kajian Kinerja Pelayanan General Cargo Terminal Jamrud Di Pelabuhan Tanjung Perak Surabaya

Directory of Open Access Journals (Sweden)

Ayu Fajar Ulfany

2018-02-01

Full Text Available Terminal Jamrud is a busy terminal among three others terminals run by PT. Pelabuhan Indonesia III branch of Tanjung Perak that serving general goods cargoes and dry bulk both dosmetically and internationally. The source of the problem to increase terminal performance are capacity building, efficiency, productivity and environment. The objectives of this study were to identify the existing performance of loading and unloading of general cargo and to arrange strategies for the development of Terminal Jamrud at Tanjung Perak Port using SWOT analysis. Based on secondary data: 1 the best operational performance of service is the productivity of loading and unloading of general cargo, 2 the best performance is the approach time (AT, 3 the waiting time (TW has not fulfilled the expected achievement as it is stil below the standard, 4 attributes of utility services, non-container terminal dock facilities, SOR and YOR still needs to be improved. The development strategies of Terminal Jamrud at kuadran I i.e grapid rowth strategy.

Physics Detector Simulation Facility Phase II system software description

International Nuclear Information System (INIS)

Scipioni, B.; Allen, J.; Chang, C.; Huang, J.; Liu, J.; Mestad, S.; Pan, J.; Marquez, M.; Estep, P.

1993-05-01

This paper presents the Physics Detector Simulation Facility (PDSF) Phase II system software. A key element in the design of a distributed computing environment for the PDSF has been the separation and distribution of the major functions. The facility has been designed to support batch and interactive processing, and to incorporate the file and tape storage systems. By distributing these functions, it is often possible to provide higher throughput and resource availability. Similarly, the design is intended to exploit event-level parallelism in an open distributed environment

Description and Results: Antenna Measurement Facility Comparisons [Measurements Corner

DEFF Research Database (Denmark)

Alberica Saporetti, Maria; Foged, Lars; Sierra Castañer, Manuel

2017-01-01

In recent years, formalized facility comparison activities have become important for the documentation and validation of laboratory proficiency and competence and mandatory for achieving accreditation such as that of the International Organization for Standardization (ISO) 17025 or similar...... for Antennas (VISTA) IC1102, including still ongoing campaigns [3]-[5]. Results of these activities have led to improvements in antenna measurement procedures and protocols in facilities and standards [6], [7]. Due to the direct benefits available to the participants, the activities have been very successful...

Disposal facility in Olkiluoto, description of above ground facilities in tunnel transport alternative

International Nuclear Information System (INIS)

Kukkola, T.

2006-11-01

The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or a by vehicle along the access tunnel. (orig.)

Disposal facility in olkiluoto, description of above ground facilities in lift transport alternative

International Nuclear Information System (INIS)

Kukkola, T.

2006-11-01

The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or by a vehicle along the access tunnel. (orig.)

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A

International Nuclear Information System (INIS)

Bowman, R.C.

1994-04-01

This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification

Facile synthesis of 2,5-disubstituted thiazoles from terminal alkynes, sulfonyl azides, and thionoesters.

Science.gov (United States)

Miura, Tomoya; Funakoshi, Yuuta; Fujimoto, Yoshikazu; Nakahashi, Junki; Murakami, Masahiro

2015-05-15

A sequential procedure for the synthesis of 2,5-disubstituted thiazoles from terminal alkynes, sulfonyl azides, and thionoesters is reported. A copper(I)-catalyzed 1,3-dipolar cycloaddition of terminal alkynes with sulfonyl azides affords 1-sulfonyl-1,2,3-triazoles, which then react with thionoesters in the presence of a rhodium(II) catalyst. The resulting 3-sulfonyl-4-thiazolines subsequently aromatize into the corresponding 2,5-disubstituted thiazoles by elimination of the sulfonyl group.

Chemical Transfer (Single Small-Scale) Facility

Data.gov (United States)

Federal Laboratory Consortium — Description/History: Chemistry laboratoryThe Chemical Transfer Facility (CTF)  is the only U.S. single small-scale  facility, a single repository for the Army’s...

NTES laser facility for physics experiments

International Nuclear Information System (INIS)

Christie, D.J.; Foley, R.J.; Frank, D.N.

1989-01-01

This paper discusses the following topics on the NTES laser facility: Mission Statement and Project Description; Experiment Area; High-Energy, Double-Pass Laser; Facilities; Laser Control and Data Acquisition; and Auxiliary Lasers

30 CFR 780.38 - Support facilities.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 780.38 Section 780.38... Support facilities. Each applicant for a surface coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within the...

30 CFR 784.30 - Support facilities.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 784.30 Section 784.30... Support facilities. Each applicant for an underground coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within the...

The quality of service in passenger transport terminals

Science.gov (United States)

Oprea, C.; Roşca, E.; Popa, M.; Ilie, A.; Dinu, O.; Roşca, M.

2016-11-01

The quality of service in transport terminals is differently perceived by engineers, economists, transport operators and sociologists. The traveler's perception is nevertheless decisive. The quality of service is well connected with the inside design of terminals, with the facilities in terminals and with the provided service standards. In order to provide a high level of service, the activities taking place in the public transport terminal and the maximum travelers flow size must be carefully analyzed and dimensioned. The purpose of modelling is to find the best route for each traveler from origin (entrance) to destination (exit) through all the intermediate service points, taking into consideration the instant network conditions. In developing the model we consider the walking, the waiting and the serving time. Using a simulation program written in ARENA we determine the waiting time. For validation, the model is used to evaluate the performance level in Bucharest Basarab station. By comparing the total walking distance for the possible routes and the utility function that describes the utility of all activities from entrance to exit we can find the optimal route.

Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

International Nuclear Information System (INIS)

1997-01-01

This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns

Chinese very small aperture terminal system for ministries

Science.gov (United States)

Dan, Sen

The objective and technologic approach of the Chinese very small aperture terminal (VSAT) system of data communications is described in this paper. The system is primarily designed for the management business of many governmental ministries and administrations. It consists of a centralized processing and switching facility and a number of groups of remote terminals. The network is constructed in a star configuration because of simplicity and the inherent nature of the management business. Either Intelsat of Chinese domestic communications satellite can be used for the space segment. The system performance has been verified by field trials. Some results of system analysis can be used for traffic design.

A description of the demonstration Integral Fast Reactor fuel cycle facility

International Nuclear Information System (INIS)

Courtney, J.C.; Carnes, M.D.; Dwight, C.C.; Forrester, R.J.

1991-01-01

A fuel examination facility at the Idaho National Engineering Laboratory is being converted into a facility that will electrochemically process spent fuel. This is an important step in the demonstration of the Integral Fast Reactor concept being developed by Argonne National Laboratory. Renovations are designed to bring the facility up to current health and safety and environmental standards and to support its new mission. Improvements include the addition of high-reliability earthquake hardened off-gas and electrical power systems, the upgrading of radiological instrumentation, and the incorporation of advances in contamination control. A major task is the construction of a new equipment repair and decontamination facility in the basement of the building to support operations

Enclosed Small and Medium Caliber Firing Experimental Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility conducts completely instrumented terminal ballistics experimental tests with small and medium-caliber tungsten alloy penetrators against advanced armor...

Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

International Nuclear Information System (INIS)

Pettersson, Stig; Forsgren, Ebbe; Lange, Fritz

2002-04-01

ground. The proposal is based on a hypothetical inland location with a rail link. The report describes a layout with a spiral ramp as access to the deposition area and with a single operational area above ground. The ramp will be used as a transport route for heavy and bulky transports. A shaft, that connects the operational area with the central area of the deposition area, is used for utility systems and for staff transports between the surface and the deposition area. It has been assumed that the deposition areas and the central area are on the same level. The appendix, describing a two level alternative, shows how the underground area could be arranged if the deposition area for regular operation were to be divided into two levels. The facility description concentrates on the situation during regular operation. It also describes the gradual expansion programme, including land requirements and connections to existing infrastructure. The report concludes with some perspective sketches, which give a vision of how the repository might look when ready for operation. This facility description is a translation of the Swedish SKB report R-02-18. It is important to note that the report gives an example of one possible design for the deep repository. Many issues concerning system design, functional solutions, layout and design ought to be investigated further before deciding on the final design

Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

Energy Technology Data Exchange (ETDEWEB)

Pettersson, Stig [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Forsgren, Ebbe [SwedPower AB, Stockholm (Sweden); Lange, Fritz [Lange Art AB, Stockholm (Sweden)

2002-04-01

below ground. The proposal is based on a hypothetical inland location with a rail link. The report describes a layout with a spiral ramp as access to the deposition area and with a single operational area above ground. The ramp will be used as a transport route for heavy and bulky transports. A shaft, that connects the operational area with the central area of the deposition area, is used for utility systems and for staff transports between the surface and the deposition area. It has been assumed that the deposition areas and the central area are on the same level. The appendix, describing a two level alternative, shows how the underground area could be arranged if the deposition area for regular operation were to be divided into two levels. The facility description concentrates on the situation during regular operation. It also describes the gradual expansion programme, including land requirements and connections to existing infrastructure. The report concludes with some perspective sketches, which give a vision of how the repository might look when ready for operation. This facility description is a translation of the Swedish SKB report R-02-18. It is important to note that the report gives an example of one possible design for the deep repository. Many issues concerning system design, functional solutions, layout and design ought to be investigated further before deciding on the final design.

A valiant little terminal: A VLT user's manual

Energy Technology Data Exchange (ETDEWEB)

Weinstein, A.

1990-12-01

This report is a manual for the valiant little terminal. Information covered in this report is as follow: an introduction to VLT; installation; starting up; text screen menus; graphics screen menus; introduction to VLT's scripting facility; quick reference section; and troubleshooting.

International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices.

International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

International Nuclear Information System (INIS)

2002-01-01

Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices

The functional improvement and reduction of operators' work at LNG receiving terminal

International Nuclear Information System (INIS)

Tomiyama, H.

1997-01-01

The Tokyo Gas Negishi Terminal has undergone a series of major changes since starting operation in 1966, including a change in the main feedstock from oil to LNG, and expansion of processing volume and scale. Control of the terminal has been in the form of centralized control and monitoring from a central control room. High technical levels have been maintained, this being one of the first terminals to adopt direct digital control (DDC) as the technology became available. In 1995, a distributed control system (DCS) was introduced as part of a large-scale redevelopment project at the Negishi Terminal, extending the scope of operations and monitoring by operators by full automation of controls, and improvement of functions including integration and upgrading of monitoring. The result has been a significant reduction in the workload on operators. The installation of these functions required further investment of around 1 billion yen, in addition to the cost of renewal of the facility. In spite of the major expansion of the range of facilities under control, the number of operators working 24-hours shifts has been reduced, and over 15 years cost reductions equivalent to around twice the investment cost are expected to be made. (au)

Stereoselective Carbonyl Olefination with Fluorosulfoximines: Facile Access to Z or E Terminal Monofluoroalkenes.

Science.gov (United States)

Liu, Qinghe; Shen, Xiao; Ni, Chuanfa; Hu, Jinbo

2017-01-09

Terminal monofluoroalkenes are important structural motifs in the design of bioactive compounds, such as homeostasis regulators and mechanism-based enzyme inhibitors. However, it is difficult to control the stereoselectivity of known carbonyl olefination reactions, and olefin metathesis is limited to disubstituted terminal monofluoroalkenes. Although sulfoximines have been used extensively in organic synthesis, reports on their use in carbonyl olefination reactions have not appeared to date. Herein, we report highly stereoselective carbonyl monofluoroolefination with a fluorosulfoximine reagent. The potential of this method is demonstrated by the synthesis of MDL 72161 and by the late-stage monofluoromethylenation of complex molecules, such as haloperidol and steroid derivatives. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

PUREX facility preclosure work plan

International Nuclear Information System (INIS)

Engelmann, R.H.

1997-01-01

This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D)

Radio Sensor for Monitoring of UMTS Mobile Terminals

Directory of Open Access Journals (Sweden)

F. Kozak

2014-06-01

Full Text Available Relatively simple and low-cost radio sensor for monitoring of 3rd generation (3G UMTS mobile terminals (i.e., phones has been designed and practically tested. The main purpose of this sensor is to serve as an extending module that can be installed into systems used for monitoring of standard 2nd generation (2G GSM and DCS mobile phones in highly guarded buildings and areas. Since the transmitted powers of UMTS mobile terminals can be very low in relation to GSM and DCS specifications, the new UMTS sensor is based on a highly sensitive receiver and additional signal processing. The radio sensor was practically tested in several scenarios representing worst-case mobile terminal - base station relations. The measured detection ranges attain values from approx. 11 m inside of rooms to more than 30 m in corridors, which seems to be sufficient for the expected application. Results of all performed tests correspond fairly well with the presented theoretical descriptions. An extended version of the radio sensor can be used for monitoring of mobile terminals of all existing voice or data formats.

System description of the Repository-Only System for the FY 1990 systems integration program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs

Nuclear facility decommissioning and site remedial actions

International Nuclear Information System (INIS)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

Nuclear facility decommissioning and site remedial actions

Energy Technology Data Exchange (ETDEWEB)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

78 FR 75359 - Waterway Suitability Assessment for Construction and Operation of Liquefied Gas Terminals; Orange...

Science.gov (United States)

2013-12-11

... Assessment for Construction and Operation of Liquefied Gas Terminals; Orange, TX AGENCY: Coast Guard, DHS... waterfront facility handling and storing Liquefied Hazardous Gas (LHG) at its Orange, Texas facility. The... LHG marine traffic in the associated waterway. INVISTA, S.a.r.l. located in Orange, Texas submitted an...

CASDAC system: Data Terminal Equipment user's guide

International Nuclear Information System (INIS)

Yamamoto, Yoichi; Koyama, Kinji

1993-03-01

The CASDAC (Containment And Surveillance Data Authenticated Communication) system has been developed by JAERI for nuclear safeguards and physical protection of nuclear material. This system is a remote monitoring system for continual verification of security and safeguards status of nuclear material. The CASDAC system consists of two subsystems, one of them is a Grand Command Center (GCC) subsystem and the other is a facility subsystem. This report describes the outline and usage of the Data Terminal Equipment (DTE), which makes available of message data communication between the GCC and a facility subsystem. This work has been carried out in the framework of Japan Support Programme for Agency Safeguards (JASPAS) as a project, JA-1. (author)

Alternatif Lokasi Terminal Sebagai Pusat Pertumbuhan Ekonomi di Doloksanggul Kabupaten Humbang Hasundutan

Directory of Open Access Journals (Sweden)

Jusmar Effendi Simamora

2014-08-01

Full Text Available Doloksanggul as the Capital District of Humbang Hasundutan also as the center economic growth until now has not had a terminal infrastructure. The result appears terminal shadows that make the city crowded and poor quality of public transport services, so that the internal and external connectivity hub disrupted economic growth. While the terminal as one element of ground transportation can lead to multiple economic effects (multiplier effect to the local and regional economy, so it has a very strategic role in supporting economic growth centers. This study aims to determine the location of the terminal is capable of supporting Doloksanggul as the center of economic growth in the District Humbang Hasundutan through assessment criteria used. To achieve the research objectives used a qualitative-descriptive and quantitative-descriptive approach which is using purposive sampling techniques, by restricting the respondent only directly related to the problem, namely regulators, operators and users (passengers. The analytical method used is the method of Analytic Hierarchy Process (AHP, because it is a flexible method of decision-making by combining a variety of considerations to obtain multi-criteria problem solving. The formulated criteria are the easies of accessibility to enter and from the terminal location, the availability of transportation networks, the ultimate destination of public transport track AKAP/AKDP, adjacent to the central market, located in the city center. The alternatives terminal location are located in the Bonanionan village, the Pasaribu village and the Simangaronsang village. Based on the results of the analysis found that the best location is the Bonanionan village with value of 0.6022 (60.22% followed the Pasaribu village with value of 0.3073 (30.73% and the last is the Simangaronsang village with value of 0.0905 (9.05%.

WRAP Module 1 data management system (DMS) software design description (SDD)

International Nuclear Information System (INIS)

Weidert, J.R.

1996-01-01

Revision 2 of the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) Preliminary Software Design Description (PSDD) provides a high-level design description of the system. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility. The WRAP 1 DMS SDD is used as the primary medium for communication software design information. This release provides design descriptions for the following process modules produced under Phase 1 of the development effort: Receiving Drum or Box Containers Process Routing and Picklists; Waste Inventory by Location and/or Container Relationships; LLW Process Glovebox Facility Radiologic Material Inventory Check (partial); Shipping (partial production); Drum or Box NDE Operations; and Drum or Box NDA Operations Data Review (partial production). In addition, design descriptions are included for the following process modules scheduled for development under Phases 2 and 3: Activity Comment; LLW RWM Glovebox Sample Management; TRU Process Glovebox; TRU RWM Glovebox; and TRUPACT Processing. Detailed design descriptions for Reports and Facility Metrics have also been provided for in Revision 2 of this document

Environmental Assessment on the leasing of the Strategic Petroleum Reserve, St. James Terminal, St. James Parish, Louisiana

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy (DOE) proposes to lease the Strategic Petroleum Reserve's (SPR) St. James Terminal to private industry. The St. James Terminal consists of six storage tanks, a pumping station, two maine docks and ancillary facilities. DOE believes that the St. James Terminal presents an opportunity to establish a government- industry arrangement that could more effectively use this asset to serve the nations's oil distribution needs, reduce the operational cost of the SPR, and provide a source of revenue for the Government. DOE solicited interest in leasing its distribution facilities in a notice published March 16, 1994. In response, industry has expressed interest in leasing the St. James Terminal, as well as several DOE pipelines, to enhance the operation of its own facilities or to avoid having to construct new ones. Under such a lease, industry use would be subordinate to DOE use in the event of a national energy emergency. This Environmental Assessment describes the proposed leasing operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) OF 1969 and has issued the Finding of No Significant Impact (FONSI)

Withholding or termination of resuscitation in pediatric out-of-hospital traumatic cardiopulmonary arrest.

Science.gov (United States)

Fallat, Mary E

2014-04-01

This multiorganizational literature review was undertaken to provide an evidence base for determining whether or not recommendations for out-of-hospital termination of resuscitation could be made for children who are victims of traumatic cardiopulmonary arrest. Although there is increasing acceptance of out-of-hospital termination of resuscitation for adult traumatic cardiopulmonary arrest when there is no expectation of a good outcome, children are routinely excluded from state termination-of-resuscitation protocols. The decision to withhold resuscitative efforts in a child under specific circumstances (decapitation or dependent lividity, rigor mortis, etc) is reasonable. If there is any doubt as to the circumstances or timing of the traumatic cardiopulmonary arrest, under the current status of limiting termination of resuscitation in the field to persons older than 18 years in most states, resuscitation should be initiated and continued until arrival to the appropriate facility. If the patient has arrested, resuscitation has already exceeded 30 minutes, and the nearest facility is more than 30 minutes away, involvement of parents and family of these children in the decision-making process with assistance and guidance from medical professionals should be considered as part of an emphasis on family-centered care, because the evidence suggests that either death or a poor outcome is inevitable.

Terminator Operon Reporter: combining a transcription termination switch with reporter technology for improved gene synthesis and synthetic biology applications.

Science.gov (United States)

Zampini, Massimiliano; Mur, Luis A J; Rees Stevens, Pauline; Pachebat, Justin A; Newbold, C James; Hayes, Finbarr; Kingston-Smith, Alison

2016-05-25

Synthetic biology is characterized by the development of novel and powerful DNA fabrication methods and by the application of engineering principles to biology. The current study describes Terminator Operon Reporter (TOR), a new gene assembly technology based on the conditional activation of a reporter gene in response to sequence errors occurring at the assembly stage of the synthetic element. These errors are monitored by a transcription terminator that is placed between the synthetic gene and reporter gene. Switching of this terminator between active and inactive states dictates the transcription status of the downstream reporter gene to provide a rapid and facile readout of the accuracy of synthetic assembly. Designed specifically and uniquely for the synthesis of protein coding genes in bacteria, TOR allows the rapid and cost-effective fabrication of synthetic constructs by employing oligonucleotides at the most basic purification level (desalted) and without the need for costly and time-consuming post-synthesis correction methods. Thus, TOR streamlines gene assembly approaches, which are central to the future development of synthetic biology.

Thermal operations conditions in a national waste terminal storage facility

International Nuclear Information System (INIS)

1976-09-01

Some of the major technical questions associated with the burial of radioactive high-level wastes in geologic formations are related to the thermal environments generated by the waste and the impact of this dissipated heat on the surrounding environment. The design of a high level waste storage facility must be such that the temperature variations that occur do not adversely affect operating personnel and equipment. The objective of this investigation was to assist OWI by determining the thermal environment that would be experienced by personnel and equipment in a waste storage facility in salt. Particular emphasis was placed on determining the maximum floor and air temperatures with and without ventilation in the first 30 years after waste emplacement. The assumed facility design differs somewhat from those previously analyzed and reported, but many of the previous parametric surveys are useful for comparison. In this investigation a number of 2-dimensional and 3-dimensional simulations of the heat flow in a repository have been performed on the HEATING5 and TRUMP heat transfer codes. The representative repository constructs used in the simulations are described, as well as the computational models and computer codes. Results of the simulations are presented and discussed. Comparisons are made between the recent results and those from previous analyses. Finally, a summary of study limitations, comparisons, and conclusions is given

Decommissioning of Facilities. General Safety Requirements. Pt. 6

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-15

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

An Economic Evaluation of Onshore and Floating Liquefied Natural Gas Receiving Terminals: the Case Study of Indonesia

Science.gov (United States)

Giranza, M. J.; Bergmann, A.

2018-05-01

Indonesia has abundant natural gas resources, however the primary fuel used for electricity generation is coal and oil. Insufficient natural gas infrastructure with-in the country acts as a barrier to increased natural gas usage. In Indonesia LNG is the most efficient and effective method for distributing natural gas given the difficult geographical conditions, the world’s largest archipelago and located in a deep sea area. The Government is planning to initiate natural gas imports by 2019 to meet the country’s energy demands. In order to allocate adequate amounts of natural gas across the geographic regions Indonesia must build more LNG regasification terminals. The Indonesia government has not yet determined if the additional regasification terminals will be floating or land-based facilities. This paper assesses the two options and identifies which facility attains greater profitability. The financial analysis of investing in the Sorong LNG regasification terminal project is conducted using NPV, IRR, and sensitivity analysis. This analysis demonstrates that FSRU facilities have greater economic viability than onshore LNG regasification facilities. The FSRU project earns greater than a 12% IRR as compared to a negative IRR earned by an onshore project. The government can make the onshore projects viable by increasing the sales fee from US10.00/MMBTU to US10.60/MMBTU.

DeBeNe Test Facilities for Fast Breeder Development

International Nuclear Information System (INIS)

Storz, R.

1980-10-01

This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

10 CFR 75.10 - Facility information.

Science.gov (United States)

2010-01-01

...) The identification of the facility, stating its general character, purpose, nominal capacity (thermal... used for routine purposes; (2) A description of the general arrangement of the facility with reference... information must be submitted: (1) Regarding a modification of a type described in the license or certificate...

Facility effluent monitoring plan for the 324 Facility

International Nuclear Information System (INIS)

1994-11-01

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Physics detector simulation facility system software description

International Nuclear Information System (INIS)

Allen, J.; Chang, C.; Estep, P.; Huang, J.; Liu, J.; Marquez, M.; Mestad, S.; Pan, J.; Traversat, B.

1991-12-01

Large and costly detectors will be constructed during the next few years to study the interactions produced by the SSC. Efficient, cost-effective designs for these detectors will require careful thought and planning. Because it is not possible to test fully a proposed design in a scaled-down version, the adequacy of a proposed design will be determined by a detailed computer model of the detectors. Physics and detector simulations will be performed on the computer model using high-powered computing system at the Physics Detector Simulation Facility (PDSF). The SSCL has particular computing requirements for high-energy physics (HEP) Monte Carlo calculations for the simulation of SSCL physics and detectors. The numerical calculations to be performed in each simulation are lengthy and detailed; they could require many more months per run on a VAX 11/780 computer and may produce several gigabytes of data per run. Consequently, a distributed computing environment of several networked high-speed computing engines is envisioned to meet these needs. These networked computers will form the basis of a centralized facility for SSCL physics and detector simulation work. Our computer planning groups have determined that the most efficient, cost-effective way to provide these high-performance computing resources at this time is with RISC-based UNIX workstations. The modeling and simulation application software that will run on the computing system is usually written by physicists in FORTRAN language and may need thousands of hours of supercomputing time. The system software is the ''glue'' which integrates the distributed workstations and allows them to be managed as a single entity. This report will address the computing strategy for the SSC

Non-terminal blood sampling techniques in guinea pigs.

Science.gov (United States)

Birck, Malene M; Tveden-Nyborg, Pernille; Lindblad, Maiken M; Lykkesfeldt, Jens

2014-10-11

Guinea pigs possess several biological similarities to humans and are validated experimental animal models(1-3). However, the use of guinea pigs currently represents a relatively narrow area of research and descriptive data on specific methodology is correspondingly scarce. The anatomical features of guinea pigs are slightly different from other rodent models, hence modulation of sampling techniques to accommodate for species-specific differences, e.g., compared to mice and rats, are necessary to obtain sufficient and high quality samples. As both long and short term in vivo studies often require repeated blood sampling the choice of technique should be well considered in order to reduce stress and discomfort in the animals but also to ensure survival as well as compliance with requirements of sample size and accessibility. Venous blood samples can be obtained at a number of sites in guinea pigs e.g., the saphenous and jugular veins, each technique containing both advantages and disadvantages(4,5). Here, we present four different blood sampling techniques for either conscious or anaesthetized guinea pigs. The procedures are all non-terminal procedures provided that sample volumes and number of samples do not exceed guidelines for blood collection in laboratory animals(6). All the described methods have been thoroughly tested and applied for repeated in vivo blood sampling in studies within our research facility.

Environmental Assessment on the leasing of the Strategic Petroleum Reserve, St. James Terminal, St. James Parish, Louisiana

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

The US Department of Energy (DOE) proposes to lease the Strategic Petroleum Reserve`s (SPR) St. James Terminal to private industry. The St. James Terminal consists of six storage tanks, a pumping station, two maine docks and ancillary facilities. DOE believes that the St. James Terminal presents an opportunity to establish a government- industry arrangement that could more effectively use this asset to serve the nations`s oil distribution needs, reduce the operational cost of the SPR, and provide a source of revenue for the Government. DOE solicited interest in leasing its distribution facilities in a notice published March 16, 1994. In response, industry has expressed interest in leasing the St. James Terminal, as well as several DOE pipelines, to enhance the operation of its own facilities or to avoid having to construct new ones. Under such a lease, industry use would be subordinate to DOE use in the event of a national energy emergency. This Environmental Assessment describes the proposed leasing operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) OF 1969 and has issued the Finding of No Significant Impact (FONSI).

Facility information system `SOINS-IIS`; Shisetsu joho kanri system `SOINS-IIS`

Energy Technology Data Exchange (ETDEWEB)

Shimaoka, S.; Watanabe, M.; Mizuno, Y. [Fuji Electric Co. Ltd., Tokyo (Japan)

1998-07-10

With the informatization in the industry, office space is becoming the center of business activities. Also as to the facility control, a facility control system is required which is added with functions of information service to users and the management support system, in addition to the conventional system used mainly for equipment maintenance. Fuji Electric Co. developed a facility information control system, SOINS-IIS (social information system-infrastructure information system), into which the above-mentioned functions were integrated. The features of the system were presented in examples of the introduction to Ichibankan, YRP (Yokosuka Research Park) Center and R and D Center, NTT DoCoMo. The system roughly has an information service function for facility users, function of management for office staff such as tenant management and bill management, management support function for facility owners and planning departments. Beside the above-mentioned functions, in case of YRP Center, for example, the system has functions of management of reservation of meeting rooms, etc., terminal display of common use information and terminal display of information, and many other management support functions. 10 figs.

Fusion materials irradiation test facility: description and status

International Nuclear Information System (INIS)

Trego, A.L.; Parker, E.F.; Hagan, J.W.

1982-01-01

The Fusion Materials Irradiation Test (FMIT) Facility will generate a high-flux, high-energy neutron source that will provide a fusion-like radiation environment for fusion reactor materials development. The neutrons will be produced in a nuclear stripping reaction by impinging a 35 MeV beam of deuterons from an Alvarez-type linear accelerator on a flowing lithium target. The target will be located in a test cell which will provide an irradiation volume of over 750l within which 10 cm 3 will have an average neutron flux of greater than 1.4 x 10 15 n/cm 2 -s and 500 cm 3 an average flux of greater than 2.2 by 10 14 n/cm 2- s with an expected availability factor greater than 65%. The projected fluence within the 10 cm 3 high flux region of FMIT will effect damage upon the materials test specimens to 30 dpa (displacements per atom) for each 90 day irradiation period. This irradiation flux volume will be at least 500 times larger than that of any other facility with comparable neutron energy and will fully meet the fusion materials damage research objective of 100 dpa within three years for the first round of tests

Full-scale mark II CRT program facility description report

International Nuclear Information System (INIS)

Namatame, Ken; Kukita, Yutaka; Ito, Hideo; Yamamoto, Nobuo; Shiba, Masayoshi

1980-03-01

Started in fiscal year 1977, the Full-Scale Mark II CRT (Containment Response Test) Program is proceeding for the period of five years. The primary objective of the CRT Program is to provide a data base for evaluation of the pressure suppression pool hydrodynamic loads associated with a postulated loss-of-coolant accident in the BWR Mark II containment system. The test facility was designed and constructed from fiscal year 1977 to 1978, and completed in March 1979. It is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report describes design concepts, dimensions and constructions of the test facility, as well as specifications, locations and installation schemes of the measuring equipments. Results of soil structure inspection, vacuum breaker test and shaker test of the containment shell are given in the appendices. (author)

PUREX facility hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1994-01-01

This report documents the hazards assessment for the Plutonium Uranium Extraction Plant (PUREX) located on the US Department of Energy (DOE) Hanford Site. Operation of PUREX is the responsibility of Westinghouse Hanford Company (WHC). This hazards assessment was conducted to provide the emergency planning technical basis for PUREX. DOE Order 5500.3A requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification. In October of 1990, WHC was directed to place PUREX in standby. In December of 1992 the DOE Assistant Secretary for Environmental Restoration and Waste Management authorized the termination of PUREX and directed DOE-RL to proceed with shutdown planning and terminal clean out activities. Prior to this action, its mission was to reprocess irradiated fuels for the recovery of uranium and plutonium. The present mission is to establish a passively safe and environmentally secure configuration at the PUREX facility and to preserve that condition for 10 years. The ten year time frame represents the typical duration expended to define, authorize and initiate follow-on decommissioning and decontamination activities

Computing facility at SSC for detectors

International Nuclear Information System (INIS)

Leibold, P.; Scipiono, B.

1990-01-01

A description of the RISC-based distributed computing facility for detector simulaiton being developed at the SSC Laboratory is discussed. The first phase of this facility is scheduled for completion in early 1991. Included is the status of the project, overview of the concepts used to model and define system architecture, networking capabilities for user access, plans for support of physics codes and related topics concerning the implementation of this facility

78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

Science.gov (United States)

2013-01-28

... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

Optimal LNG (liquefied natural gas) regasification scheduling for import terminals with storage

International Nuclear Information System (INIS)

Trotter, Ian M.; Gomes, Marília Fernandes Maciel; Braga, Marcelo José; Brochmann, Bjørn; Lie, Ole Nikolai

2016-01-01

We describe a stochastic dynamic programming model for maximising the revenue generated by regasification of LNG (liquefied natural gas) from storage tanks at importation terminals in relation to a natural gas spot market. We present three numerical resolution strategies: a posterior optimal strategy, a rolling intrinsic strategy and a full option strategy based on a least-squares Monte Carlo algorithm. We then compare model simulation results to the observed behaviour of three LNG importation terminals in the UK for the period April 2011 to April 2012, and find that there was low correlation between the observed regasification decisions of the operators and those suggested by the three simulated strategies. However, the actions suggested by the model simulations would have generated significantly higher revenues, suggesting that the facilities might have been operated sub-optimally. A further numerical experiment shows that increasing the storage and regasification capacities of a facility can significantly increase the achievable revenue, even without altering the amount of LNG received, by allowing operators more flexibility to defer regasification. - Highlights: • We present a revenue maximisation model for LNG (liquefied natural gas) storage tanks at import terminals. • Three resolution strategies: posterior optimal, rolling intrinsic and full option. • The full option strategy is based on a least-squares Monte Carlo algorithm. • Model simulations show potential for higher revenue in three UK LNG terminals. • Numerical experiments show how storage and regasification capacities affect revenue.

Engine Environment Research Facility (EERF)

Data.gov (United States)

Federal Laboratory Consortium — Description: This facility supports research and development testing of the behavior of turbine engine lubricants, fuels and sensors in an actual engine environment....

Incineration facilities for treatment of radioactive wastes: a review

Energy Technology Data Exchange (ETDEWEB)

Perkins, B.L.

1976-02-01

A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant.

Incineration facilities for treatment of radioactive wastes: a review

International Nuclear Information System (INIS)

Perkins, B.L.

1976-02-01

A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant

Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1989

International Nuclear Information System (INIS)

Raddatz, C.T.

1992-04-01

This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC 1 licensees during the years 1969 through 1989. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC 1 licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1989 annual reports submitted by about 448 licensees indicated that approximately 216,294 individuals were monitored 111,000 of whom were monitored by nuclear power facilities. They incurred an average individual does of 0.18 rem (cSv) and an average measurable dose of 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,535 individuals completed their employment with one or more of the 448 covered licensees during 1989. Some 76,561 of these individuals terminated from power reactor facilities, and about 10, 344 of them were considered to be transient workers who received an average dose of 0.64 rem (cSv)

Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1988

International Nuclear Information System (INIS)

Raddatz, C.T.

1991-07-01

This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1988. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1988 annual reports submitted by about 429 licensees indicated that approximately 220,048 individuals were monitored, 113,00 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.20 rem (cSv) and an average measurable dose of 0.41 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,072 individuals completed their employment with one or more of the 429 covered licensees during 1988. Some 80,211 of these individuals terminated from power reactor facilities, and about 8,760 of them were considered to be transient workers who received an average dose of 0.27 rem (cSv). 17 refs., 11 figs., 29 tabs

Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1991

International Nuclear Information System (INIS)

Raddatz, C.T.

1993-07-01

This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1991. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1991 annual reports submitted by about 436 licensees indicated that approximately 206,732 individuals were monitored, 182,334 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.15 rem (cSv) and an average measurable dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 96,231 individuals completed their employment with one or more of the 436 covered licensees during 1991. Some 68,115 of these individuals terminated from power reactor facilities, and about 7,763 of them were considered to be transient workers who received an average dose of 0.52 rem (cSv)

Development of a multi-media crew-training program for the terminal configured vehicle mission simulator

Science.gov (United States)

Rhouck, J. A.; Markos, A. T.

1980-01-01

This paper describes the work being done at the National Aeronautics and Space Administration's (NASA) Langley Research Center on the development of a multi-media crew-training program for the Terminal Configured Vehicle (TCV) Mission Simulator. Brief descriptions of the goals and objectives of the TCV Program and of the TCV Mission Simulator are presented. A detailed description of the training program is provided along with a description of the performance of the first group of four commercial pilots to be qualified in the TCV Mission Simulator.

Several new thermo-hydraulic test facilities in NPIC

International Nuclear Information System (INIS)

Ye Shurong; Sun Yufa; Ji Fuyun; Zong Guifang; Guo Zhongchuan

1997-01-01

Several new thermo-hydraulic test facilities are under construction in Nuclear Power Institute of Chinese (NPIC) at Chengdu. These facilities include: 1. Nuclear Power Component Comprehensive Test Facility. 2. Reactor Hydraulic Modeling Test Facility. 3. Control Rod Drive Line Hydraulic Test Facility. 4. Large Scale Thermo-Hydraulic Test Facility. The construction of these facilities will make huge progress in the research and development capability of nuclear power technology in CHINA. The author will present a brief description of the design parameters flowchart and test program of these facilities

Pengaruh kualitas Udara ( Debu,COx, NOx, SOx Terminal Terhadap Gangguan Fungsi Paru Pada Pedagang Tetap Terminal Bus Induk Jawa Tengah, 2002

Directory of Open Access Journals (Sweden)

Soedjono Soedjono

2015-12-01

Full Text Available ABSTRACT Background : The high growth of motor vehicle in Central Java in 2000 reached 11,8% a year and from these number the city bus, 4,5%. This condition has seriously brought negative effect to environment. Many researchers found that the equipment of transportation and the industry are sources of air pollution, which very large and very dominant. The bus terminal is one location that is the highest air pollution than other locations because the bus terminal is a central of activities that need a transportation service. Beside that the bus terminal is a influence of sir quality dust, COx, NOx, SOx, in the bus terminal to the lung dysfunction of the permanent seller in the 15 prime bus terminals in Central Java, 2002 and to find the exposed duration, the work duration, the habit of smoking and age which can influence  the lung disfunction. Method : This was an analytic research using cross sectional approach. The samples of this research were 309 respondents (total population. The concentration of dust, COx, NOx, SOx, was directly  measured in the 15 prime bus terminals. The other data was measured by  interviewing with the sellers in the bus terminal who had been limited their ages (40 years old to down. The logistic regression analysis was used to test the influence of dust, COx, NOx, SOx, the exposed duration, the work duration, the habit of smoking and age. Result : The result of descriptive analysis shows that all variables have influence to the instance of the lung disfunction. It can be seen from the number of percentage of respondent who experienced the lung disfunction in  each variable. From analitical statistic, only the variable of anamnesis / the other diseases has influence which very significant to the instance of the lung disfunction. Other variables are risk factors to the instance of the lung disfunction. Key word : Dust, COx, NOx, SOx, concentration, interference lung – function, Seller, Bus Terminal.

Detonation Engine Research Facility (DERF)

Data.gov (United States)

Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

Au-Catalyzed Synthesis of 2-Alkylindoles from N-Arylhydroxylamines and Terminal Alkynes

Science.gov (United States)

Wang, Yanzhao; Ye, Longwu

2012-01-01

The first gold-catalyzed addition of N-arylhydroxylamines to aliphatic terminal alkynes is developed to access O-alkenyl-N-arylhydroxylamines, which undergo facile in situ sequential 3,3-rearrangements and cyclodehydrations to afford 2-alkylindoles with regiospecificity and under exceptionally mild reaction conditions. PMID:21637891

National Waste Terminal Storage Program. Progress report, October 1, 1976--September 30, 1977

International Nuclear Information System (INIS)

Asher, J.M.

1978-04-01

The National Waste Terminal Storage Program Report comprises five sections: technical projects, facility projects, planning and analysis, regulatory affairs, and public affairs. Progress made in these areas during the period October 1, 1976, to September 30, 1977, is reported

Trisonic Gas-Dynamics Facility (TGF)

Data.gov (United States)

Federal Laboratory Consortium — Description: The TGF is a two-foot square, continuous-flow, closed-circuit wind tunnel which is optimal for conducting research experiments. The facility provides a...

Facility effluent monitoring plan for the 325 Facility

International Nuclear Information System (INIS)

1998-01-01

The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Simulation of stevedoring work in the Klaipėda oil terminal

Directory of Open Access Journals (Sweden)

D. Makackas

2002-10-01

Full Text Available The paper presents the approach of developing simulation models of stevedoring work in oil terminal using aggregate approach and simulation system ARENA. Aggregate approach permits to develop formal specification of simulated systems. Aggregate specification of the system is presented as a set of interacting piece-linear aggregates. Controlling sequences are used for formal description of each piece-linear aggregate. Transformation of aggregate formal specification to ARENA system operators permits to develop a simulation model. The developed model permits to evaluate characteristics of the Klaipėda oil terminal which are used both in queuing theory and analysing timing properties of real-time systems.

Renton's Quendall Terminals on List of EPA Superfund Sites Targeted for Immediate, Intense Attention

Science.gov (United States)

EPA released the list of Superfund sites that Administrator Pruitt has targeted for intense and immediate attention, including the Quendall Terminals Site, a former creosote facility on the shore of Lake Washington in Renton, Washington.

Physics and detector simulation facility Type O workstation specifications

International Nuclear Information System (INIS)

Chartrand, G.; Cormell, L.R.; Hahn, R.; Jacobson, D.; Johnstad, H.; Leibold, P.; Marquez, M.; Ramsey, B.; Roberts, L.; Scipioni, B.; Yost, G.P.

1990-11-01

This document specifies the requirements for the front-end network of workstations of a distributed computing facility. This facility will be needed to perform the physics and detector simulations for the design of Superconducting Super Collider (SSC) detectors, and other computations in support of physics and detector needs. A detailed description of the computer simulation facility is given in the overall system specification document. This document provides revised subsystem specifications for the network of monitor-less Type 0 workstations. The requirements specified in this document supersede the requirements given. In Section 2 a brief functional description of the facility and its use are provided. The list of detailed specifications (vendor requirements) is given in Section 3 and the qualifying requirements (benchmarks) are described in Section 4

Security report on Siloe - the descriptive part. (1963)

International Nuclear Information System (INIS)

Ageron, P.; Chatoux, J.; Denielou, G.; Jacquemain, M.; Mitault, G.; Robien, E. de; Rossillon, F.

1963-01-01

This report is a full description of the site, the reactor, the building and the experimental facilities. It gives the nuclear, thermodynamic and hydrodynamic characteristics of the core. (authors) [fr

New facilities of the ECN hot cell laboratory

International Nuclear Information System (INIS)

Duijves, K.A.; Konings, R.J.M.

1996-04-01

A description is given of two recent expansions of the ECN Hot Cell Laboratory in Petten; a production facility for molybdenum-99 and an actinide laboratory, a special facility to investigate unirradiated alpha- and beta-active samples. (orig.)

Initial operation of the Holifield facility

International Nuclear Information System (INIS)

Ball, J.B.

1982-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new Pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Initial operation of the Holifield Facility

International Nuclear Information System (INIS)

Ball, J.B.

1983-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Content of system design descriptions

International Nuclear Information System (INIS)

1998-10-01

A System Design Description (SDD) describes the requirements and features of a system. This standard provides guidance on the expected technical content of SDDs. The need for such a standard was recognized during efforts to develop SDDs for safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Existing guidance related to the corresponding documents in other industries is generally not suitable to meet the needs of DOE nuclear facilities. Across the DOE complex, different contractors have guidance documents, but they vary widely from site to site. While such guidance documents are valuable, no single guidance document has all the attributes that DOE considers important, including a reasonable degree of consistency or standardization. This standard is a consolidation of the best of the existing guidance. This standard has been developed with a technical content and level of detail intended to be most applicable to safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Notwithstanding that primary intent, this standard is recommended for other systems at such facilities, especially those that are important to achieving the programmatic mission of the facility. In addition, application of this standard should be considered for systems at other facilities, including non-nuclear facilities, on the basis that SDDs may be beneficial and cost-effective

Cold Vacuum Drying facility condensate collection system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) condensate collection system (CCS). The function of the CCS is to collect cooling coil condensate from air-handling units in the CVDF and to isolate the condensate in collection tanks until the condensate is determined to be acceptable to drain to the effluent drain collection basin

Cold Vacuum Drying facility potable water system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) potable water (PW) system. The PW system provides potable water to the CVDF for supply to sinks, water closets, urinals, showers, custodial service sinks, drinking fountains, the decontamination shower, supply water to the non-PW systems, and makeup water for the de-ionized water system

System Design Description PFP Thermal Stabilization

International Nuclear Information System (INIS)

RISENMAY, H.R.

2000-01-01

The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures

HIV screening among TB patients and co-trimoxazole preventive therapy for TB/HIV patients in Addis Ababa: facility based descriptive study.

Science.gov (United States)

Denegetu, Amenu Wesen; Dolamo, Bethabile Lovely

2014-01-01

Collaborative TB/HIV management is essential to ensure that HIV positive TB patients are identified and treated appropriately, and to prevent tuberculosis (TB) in HIV positive patients. The purpose of this study was to assess HIV case finding among TB patients and Co-trimoxazole Preventive Therapy (CPT) for HIV/TB patients in Addis Ababa. A descriptive cross-sectional, facility-based survey was conducted between June and July 2011. Data was collected by interviewing 834 TB patients from ten health facilities in Addis Ababa. Both descriptive and inferential statistics were used to summarize and analyze findings. The proportion of TB patients who (self reported) were offered for HIV test, tested for HIV and tested HIV positive during their anti-TB treatment follow-up were; 87.4%, 69.4% and 20.2%; respectively. Eighty seven HIV positive patients were identified, who knew their status before diagnosed for the current TB disease, bringing the cumulative prevalence of HIV among TB patients to 24.5%. Hence, the proportion of TB patients who knew their HIV status becomes 79.9%. The study revealed that 43.6% of those newly identified HIV positives during anti-TB treatment follow-up were actually treated with CPT. However, the commutative proportion of HIV positive TB patients who were ever treated with CPT was 54.4%; both those treated before the current TB disease and during anti-TB treatment follow-up. HIV case finding among TB patients and provision of CPT for TB/HIV co-infected patients needs boosting. Hence, routine offering of HIV test and provision of CPT for PLHIV should be strengthened in-line with the national guidelines.

Overview study of LNG release prevention and control systems

Energy Technology Data Exchange (ETDEWEB)

Pelto, P.J.; Baker, E.G.; Holter, G.M.; Powers, T.B.

1982-03-01

The liquefied natural gas (LNG) industry employs a variety of release prevention and control techniques to reduce the likelihood and the consequences of accidental LNG releases. A study of the effectiveness of these release prevention and control systems is being performed. Reference descriptions for the basic types of LNG facilities were developed. Then an overview study was performed to identify areas that merit subsequent and more detailed analyses. The specific objectives were to characterize the LNG facilities of interest and their release prevention and control systems, identify possible weak links and research needs, and provide an analytical framework for subsequent detailed analyses. The LNG facilities analyzed include a reference export terminal, marine vessel, import terminal, peakshaving facility, truck tanker, and satellite facility. A reference description for these facilities, a preliminary hazards analysis (PHA), and a list of representative release scenarios are included. The reference facility descriptions outline basic process flows, plant layouts, and safety features. The PHA identifies the important release prevention operations. Representative release scenarios provide a format for discussing potential initiating events, effects of the release prevention and control systems, information needs, and potential design changes. These scenarios range from relatively frequent but low consequence releases to unlikely but large releases and are the principal basis for the next stage of analysis.

The X-Ray Pebble Recirculation Experiment (X-PREX): Facility Description, Preliminary Discrete Element Method Simulation Validation Studies, and Future Test Program

International Nuclear Information System (INIS)

Laufer, Michael R.; Bickel, Jeffrey E.; Buster, Grant C.; Krumwiede, David L.; Peterson, Per F.

2014-01-01

This paper presents a facility description, preliminary results, and future test program of the new X-Ray Pebble Recirculation Experiment (X-PREX), which is now operational and being used to collect data on the behavior of slow dense granular flows relevant to pebble bed reactor core designs. The X-PREX facility uses digital x-ray tomography methods to track both the translational and rotational motion of spherical pebbles, which provides unique experimental results that can be used to validate discrete element method (DEM) simulations of pebble motion. The validation effort supported by the X-PREX facility provides a means to build confidence in analysis of pebble bed configuration and residence time distributions that impact the neutronics, thermal hydraulics, and safety analysis of pebble bed reactor cores. Preliminary experimental and DEM simulation results are reported for silo drainage, a classical problem in the granular flow literature, at several hopper angles. These studies include conventional converging and novel diverging geometries that provide additional flexibility in the design of pebble bed reactor cores. Excellent agreement is found between the X-PREX experimental and DEM simulation results. Finally, this paper discusses additional studies in progress relevant to the design and analysis of pebble bed reactor cores including pebble recirculation in cylindrical core geometries and evaluation of forces on shut down blades inserted directly into a packed pebble bed. (author)

Wound Documentation by Using 3G Mobile as Acquisition Terminal: An Appropriate Proposal for Community Wound Care.

Science.gov (United States)

Ge, Kui; Wu, Minjie; Liu, Hu; Gong, Jiahong; Zhang, Yi; Hu, Qiang; Fang, Min; Tao, Yanping; Cai, Minqiang; Chen, Hua; Wang, Jianbo; Xie, Ting; Lu, Shuliang

2015-06-01

The increasing numbers of cases of wound disease are now posing a big challenge in China. For more convenience of wound patients, wound management in community health care centers under the supervision of a specialist at general hospitals is an ideal solution. To ensure an accurate diagnosis in community health clinics, it is important that "the same language" for wound description, which may be composed of unified format description, including wound image, must be achieved. We developed a wound information management system that was built up by acquisition terminal, wound description, data bank, and related software. In this system, a 3G mobile phone was applied as acquisition terminal, which could be used to access to the data bank. This documentation system was thought to be an appropriate proposal for community wound care because of its objectivity, uniformity, and facilitation. It also provides possibility for epidemiological study in the future. © The Author(s) 2014.

76 FR 70809 - Notice of Passenger Facility Charge (PFC) Approvals and Disapprovals

Science.gov (United States)

2011-11-15

.... Pavement condition index airfield inspection. Brief Description of Withdrawn Projects: Safety management... management services. East terminal expansion. New upper level roadway, design and construction. PFC...

Medical termination of pregnancy in general practice in Australia: a descriptive-interpretive qualitative study.

Science.gov (United States)

Dawson, Angela J; Nicolls, Rachel; Bateson, Deborah; Doab, Anna; Estoesta, Jane; Brassil, Ann; Sullivan, Elizabeth A

2017-03-14

Australian Government approval in 2012 for the use of mifepristone and misoprostol for medical termination of pregnancy (MTOP) allows general practitioners (GPs) to provide early gestation abortion in primary care settings. However, uptake of the MTOP provision by GPs appears to be low and the reasons for this have been unclear. This study investigated the provision of and referral for MTOP by GPs. We undertook descriptive-interpretive qualitative research and selected participants for diversity using a matrix. Twenty-eight semi-structured interviews and one focus group (N = 4), were conducted with 32 GPs (8 MTOP providers, 24 non MTOP providers) in New South Wales, Australia. Interviews were recorded and transcribed verbatim. A framework to examine access to abortion services was used to develop the interview questions and emergent themes identified thematically. Three main themes emerged: scope of practice; MTOP demand, care and referral; and workforce needs. Many GPs saw abortion as beyond the scope of their practice (i.e. a service others provide in specialist private clinics). Some GPs had religious or moral objections; others regarded MTOP provision as complicated and difficult. While some GPs expressed interest in MTOP provision they were concerned about stigma and the impact it may have on perceptions of their practice and the views of colleagues. Despite a reported variance in demand most MTOP providers were busy but felt isolated. Difficulties in referral to a local public hospital in the case of complications or the provision of surgical abortion were noted. Exploring the factors which affect access to MTOP in general practice settings provides insights to assist the future planning and delivery of reproductive health services. This research identifies the need for support to increase the number of MTOP GP providers and for GPs who are currently providing MTOP. Alongside these actions provision in the public sector is required. In addition

Description of work vadose drilling at the 1301-N and 1325-N facilities, 100-NR-1 operable unit

International Nuclear Information System (INIS)

1994-08-01

This description of work (DOW) details the field activities associated with the sampling of the vadose zone soils beneath the 1301-N and 1325-N cribs and trenches and will serve as a field guide for those performing the work. These activities are undertaken pursuant to the Hanford Federal Facility Agreement and Consent Order (Ecology et al., 1994a) Milestone M-16-94-01H-Tl and the June 30, 1994 Milestone Change Request M-16-94-02 (Ecology et al., 1994b). Three vadose zone borings, 1301-N-1, 1301-N-2, and 1325-N-1, will be constructed to investigate the vertical and horizontal distribution of radionuclide contamination in sediments beneath the cribs and trenches. The boreholes are also intended to intersect subsurface areas that may have been contaminated by dangerous wastes, i.e., metals, in effluent disposed during past operation of the facilities. This limited field investigation will provide data for the evaluation of remedial alternatives. Data from the investigation are expected to confirm that the cribs and trenches are high priority sites in the 100-NR-1 operable unit. Data, from the investigation will be used to evaluate alternatives for closure of the 1301-N and 1325-N sites. The contaminants of potential concern (COPCs) for the 1301-N/1325-N limited field investigation are presented in Table 1

National Waste Terminal Storage Program: configuration management plan. Volume II. Plan description

International Nuclear Information System (INIS)

1977-05-01

Purpose of the Configuration Management Plan is to provide the management discipline through which the integrity and continuity of program cost and schedule trade-off decisions which are made concerning the site selections and facilities performance, producibility, operability and supportability are recorded, communicated, and controlled by the Office of Waste Isolation

Facility safeguards at an LEU fuel fabrication facility in Japan

International Nuclear Information System (INIS)

Kuroi, H.; Osabe, T.

1984-01-01

A facility description of a Japanese LEU BWR-type fuel fabrication plant focusing on safeguards viewpoints is presented. Procedures and practices of MC and A plan, measurement program, inventory taking, and the report and record system are described. Procedures and practices of safeguards inspection are discussed and lessons learned from past experiences are reviewed

MODELS OF AIR TRAFFIC CONTROLLERS ERRORS PREVENTION IN TERMINAL CONTROL AREAS UNDER UNCERTAINTY CONDITIONS

Directory of Open Access Journals (Sweden)

Volodymyr Kharchenko

2017-03-01

Full Text Available Purpose: the aim of this study is to research applied models of air traffic controllers’ errors prevention in terminal control areas (TMA under uncertainty conditions. In this work the theoretical framework descripting safety events and errors of air traffic controllers connected with the operations in TMA is proposed. Methods: optimisation of terminal control area formal description based on the Threat and Error management model and the TMA network model of air traffic flows. Results: the human factors variables associated with safety events in work of air traffic controllers under uncertainty conditions were obtained. The Threat and Error management model application principles to air traffic controller operations and the TMA network model of air traffic flows were proposed. Discussion: Information processing context for preventing air traffic controller errors, examples of threats in work of air traffic controllers, which are relevant for TMA operations under uncertainty conditions.

Westinghouse Hanford Company risk management strategy for retired surplus facilities

International Nuclear Information System (INIS)

Taylor, W.E.; Coles, G.A.; Shultz, M.V.; Egge, R.G.

1993-09-01

This paper describes an approach that facilitates management of personnel safety and environmental release risk from retired, surplus Westinghouse Hanford Company-managed facilities during the predemolition time frame. These facilities are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 2 ) Hanford Site in Richland, Washington. The production reactors are located in the 100 Area and the chemical separation facilities are located in the 200 Area. This paper also includes a description of the risk evaluation process, shows applicable results, and includes a description of comparison costs for different risk reduction options

Cold Vacuum Drying (CVD) Electrical System Design Description

International Nuclear Information System (INIS)

SINGH, G.

2000-01-01

This system design description (SDD) provides a technical explanation of the design and operation of the electrical system for the Cold Vacuum Drying Facility (CVDF). This SDD also identifies the requirements, and the basis for the requirements and details on how the requirements have been implemented in the design and construction of the facility. This SDD also provides general guidance for the surveillance, testing, and maintenance of this system

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

Generic description of facilities at the shaft head (auxiliary entrance installations) of deep geological repositories; Generische Beschreibung von Schachtkopfanlagen (Nebenzugangsanlagen) geologischer Tiefenlager

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-10-15

In a deep geological repository, the access structures function as the link between the surface and the installations and structures at the disposal level. In the planned implementation scenarios, at least two access structures will be in operation up to the time of closure of the repository. The radioactive waste will be transported via the main access from the surface to the disposal level during emplacement operations. For the construction and operation of a deep geological repository, additional access structures are required. These auxiliary accesses and the associated surface infrastructure (e.g. shaft head installations) form the subject of this report. To provide as broad and comprehensive a description as possible, seven types of auxiliary access facilities are defined; these are characterised in line with the current status of planning and their functions and impacts are described. During construction, operation and dismantling of auxiliary access facilities, the usual conventional safety measures (inter alia) have to be observed (e.g. groundwater protection, fire prevention, facility security, accident prevention). Regarding the 'Ordinance on Protection against Major Accidents' no large quantities of hazardous materials, i.e. above the corresponding threshold quantities, are to be expected in the auxiliary access facilities. Proper handling and compliance with applicable regulations in all phases will ensure no hazard to humans and the environment. As no handling of radioactive materials is foreseen in the auxiliary access facilities, and because exhaust air and waste water from the controlled zones of a repository will, in principle, be removed via the main access and not the auxiliary accesses, a safety-relevant emission of radioactive substances and transport of contaminated material can be ruled out for the auxiliary access facilities during both normal operation and also in the case of an accident. Based on the information presented in

A facile copper(I)-catalyzed homocoupling of terminal alkynes to 1,3-diynes with diaziridinone under mild conditions

OpenAIRE

Zhu, Yingguang; Shi, Yian

2013-01-01

A novel and efficient Cu(I)-catalyzed oxidative homocoupling of terminal alkynes with diaziridinone as oxidant is described. Various terminal alkynes can be transformed into the corresponding 1,3-diynes in good yields. The reaction process is base-free, operationally simple, and amenable to gram scale.

Upgrade of the Los Alamos Plutonium Facility control system

International Nuclear Information System (INIS)

Pope, N.G.; Turner, W.J.; Brown, R.E.; Bibeau, R.A.; Davis, R.R.; Hogan, K.

1996-01-01

After 20 yrs service, the Los Alamos Plutonium Facility is undergoing an upgrade to its aging Facility Control System. The new system design includes a network of redundantly-paired programmable logic controllers that will interface with about 2200 field data points. The data communications network that has been designed includes a redundant, self-healing fiber optic data highway as well as a fiber optic ethernet. Commercially available human-machine interface software running on a UNIX-based system displays facility subsystem status operator X-terminals. Project design features, methods, costs, and schedule are discussed

303-K Radioactive Mixed-Waste Storage Facility closure plan

International Nuclear Information System (INIS)

1991-11-01

The Hanford Site, located northwest of Richland, Washington, houses reactors chemical-separation systems, and related facilities used for the production o special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 303-K Radioactive Mixed-Waste Storage Facility (303-K Facility) has been used since 1943 to store various radioactive,and dangerous process materials and wastes generated by the fuel manufacturing processes in the 300 Area. The mixed wastes are stored in US Department of Transportation (DOT)-specification containers (DOT 1988). The north end of the building was used for storage of containers of liquid waste and the outside storage areas were used for containers of solid waste. Because only the north end of the building was used, this plan does not include the southern end of the building. This closure plan presents a description of the facility, the history of materials and wastes managed, and a description of the procedures that will be followed to chose the 303-K Facility as a greater than 90-day storage facility. The strategy for closure of the 303-K Facility is presented in Chapter 6.0

Decommissioning nuclear facilities

International Nuclear Information System (INIS)

Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

1976-01-01

This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

ROSA-IV Large Scale Test Facility (LSTF) system description for second simulated fuel assembly

International Nuclear Information System (INIS)

1990-10-01

The ROSA-IV Program's Large Scale Test Facility (LSTF) is a test facility for integral simulation of thermal-hydraulic response of a pressurized water reactor (PWR) during small break loss-of-coolant accidents (LOCAs) and transients. In this facility, the PWR core nuclear fuel rods are simulated using electric heater rods. The simulated fuel assembly which was installed during the facility construction was replaced with a new one in 1988. The first test with this second simulated fuel assembly was conducted in December 1988. This report describes the facility configuration and characteristics as of this date (December 1988) including the new simulated fuel assembly design and the facility changes which were made during the testing with the first assembly as well as during the renewal of the simulated fuel assembly. (author)

A facile copper(I)-catalyzed homocoupling of terminal alkynes to 1,3-diynes with diaziridinone under mild conditions.

Science.gov (United States)

Zhu, Yingguang; Shi, Yian

2013-11-21

A novel and efficient Cu(I)-catalyzed oxidative homocoupling of terminal alkynes with diaziridinone as an oxidant is described. Various terminal alkynes can be transformed into the corresponding 1,3-diynes in good yields. The reaction process is base-free, operationally simple, and amenable to the gram scale.

National Waste Terminal Storage Program information meeting, December 7-8, 1976

International Nuclear Information System (INIS)

1976-12-01

Volume I of the report comprises copies of the slides from the talks presented at the first session of the National Waste Terminal Storage Program information meeting. The agenda for the first day included an overview of the program plus presentations on such subjects as schedules and controls, facility projects, systems studies, regulatory affairs and technical support

Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

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

Analytical methods used at model facility

International Nuclear Information System (INIS)

Wing, N.S.

1984-01-01

A description of analytical methods used at the model LEU Fuel Fabrication Facility is presented. The methods include gravimetric uranium analysis, isotopic analysis, fluorimetric analysis, and emission spectroscopy

Security report on Siloe - the descriptive part. (1963); Rapport de surete de Siloe - partie descriptive (1963)

Energy Technology Data Exchange (ETDEWEB)

Ageron, P; Chatoux, J; Denielou, G; Jacquemain, M; Mitault, G; Robien, E de; Rossillon, F [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1963-07-01

This report is a full description of the site, the reactor, the building and the experimental facilities. It gives the nuclear, thermodynamic and hydrodynamic characteristics of the core. (authors) [French] Ce rapport decrit completement le site, le reacteur, les batiments et les installations experimentales. Il donne les caracteristiques nucleaires, thermodynamiques et hydrodynamiques du coeur. (auteurs)

Cold Vacuum Drying facility fire protection system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) fire protection system (FPS). The FPS provides fire detection, suppression, and loss limitation for the CVDF structure, personnel, and in-process spent nuclear fuel. The system provides, along with supporting interfacing systems, detection, alarm, and activation instrumentation and controls, distributive piping system, isolation valves, and materials and controls to limit combustibles and the associated fire loadings

Description of the PIE facility for research reactors irradiated fuels in CNEA

International Nuclear Information System (INIS)

Bisca, A.; Coronel, R.; Homberger, V.; Quinteros, A.; Ratner, M.

2002-01-01

The PIE Facility (LAPEP), located at the Ezeiza Atomic Center (CAE), was designed to carry out destructive and non-destructive post-irradiation examinations (PIE) on research and power reactor spent fuels, reactor internals and other irradiated materials, and to perform studies related with: Station lifetime extension; Fuel performance; Development of new fuels; and Failures and determination of their causes. LAPEP is a relevant facility where research and development can be carried out. It is worth mentioning that in this facility the PIE corresponding to the Surveillance Program for the Atucha I Nuclear Power Plant (CNA-1) were successfully performed. Materials testing during the CNA-1 repair and the study of failures in fuel element plugs of the Embalse Nuclear Power Plant (CNE) were also performed. (author)

Design description of the vacuum vessel for the Advanced Toroidal Facility

International Nuclear Information System (INIS)

Chipley, K.K.; Nelson, B.E.; Vinyard, L.M.; Williamson, D.F.

1983-01-01

The Advanced Toroidal Facility (ATF) will be a stellarator experiment to investigate improvements in toroidal confinement. The vacuum vessel for this facility will provide the appropriate evacuated region for plasma containment within the helical field (HF) coils. The vessel is designed to provide the maximum reasonable volume inside the HF coils and to provide the maximum reasonable access for future diagnostics. The vacuum vessel design is at an early phase and all of the details have not been completed. The heat transfer analysis and stress analysis completed during the conceptual design indicate that the vessel will not change drastically

Operating large controlled thermonuclear fusion research facilities

International Nuclear Information System (INIS)

Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

1987-01-01

The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

Ferry Terminals and Small Craft Berthing Facilities. Design Manual 25.5.

Science.gov (United States)

1981-07-01

become water-logged and sink in a few years. Use is generally not recommended. (2) Extruded polystyrene (Styrofoam). Available in several sizes of precast...Supplemental facilities, such as boardroom, coffee- break room or snack bar, engineering room, and storage room, fol large installations. b

Exploratory shaft facility preliminary designs - Permian Basin

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Permian Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Permian Basin, Texas. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references, 13 tables

New instrument calibration facility for the DOE Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Wilkie, W.H.; Polz, E.J. [Westinghouse Savannah River Company, Aiken, SC (United States)

1993-12-31

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided.

New instrument calibration facility for the DOE Savannah River Site

International Nuclear Information System (INIS)

Wilkie, W.H.; Polz, E.J.

1993-01-01

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided

Waste Management Systems Requirements and Descriptions (SRD)

International Nuclear Information System (INIS)

Conner, C.W.

1986-01-01

The Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a system for the management of high-level radioactive waste and spent fuel in accordance with the Nuclear Waste Policy Act of 1982. The Waste Management system requirements and description document is the program-level technical baseline document. The requirements include the functions that must be performed in order to achieve the system mission and performance criteria for those functions. This document covers only the functional requirements of the system; it does not cover programmatic or procedural requirements pertaining to the processes of designing, siting and licensing. The requirements are largely based on the Nuclear Waste Policy Act of 1982, Environmental Protection Agency standards, Nuclear Regulatory Commission regulations, and DOE orders and guidance. However, nothing in this document should be construed as to relieve the DOE or its contractors from their responsibilities to comply with applicable statutes, regulations, and standards. This document also provides a brief description of the system being developed to meet the requirements. In addition to the described ''authorized system,'' a system description is provided for an ''improved-performance system'' which would include a monitored retrievable storage (MRS) facility. In the event that an MRS facility is approved by Congress, the improved-performance system will become the reference system. Neither system description includes Federal Interim Storage (FIS) capabilities. Should the need for FIS be identified, it will be included as an additional system element. The descriptions are focused on the interfaces between the system elements, rather than on the detail of the system elements themselves

Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Goldhagen, P.; Marino, S.A.; Randers-Pehrson, G.; Hall, E.J.

1986-01-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which can be used to generate a variety of well-characterized radiation beams for research in radiobiology and radiological physics. It is part of the Radiological Research Laboratory (RRL), and its operation is supported as a National Facility by the US Department of Energy. RARAF is available to all potential users on an equal basis, with priorities based on the recommendations of a Scientific Advisory Committee. Facilities and services are provided to users, but the research projects themselves must be supported separately. This chapter presents a brief description of current experiments being carried out at RARAF and of the operation of the Facility from January through June, 1986. Operation of the Facility for all of 1985 was described in the 1985 Progress Report for RARAF. The experiments described here were supported by various Grants and Contracts from NIH and DOE and by the Statens Stralskyddsinstitut of Sweden

Management control system description

Energy Technology Data Exchange (ETDEWEB)

Bence, P. J.

1990-10-01

This Management Control System (MCS) description describes the processes used to manage the cost and schedule of work performed by Westinghouse Hanford Company (Westinghouse Hanford) for the US Department of Energy, Richland Operations Office (DOE-RL), Richland, Washington. Westinghouse Hanford will maintain and use formal cost and schedule management control systems, as presented in this document, in performing work for the DOE-RL. This MCS description is a controlled document and will be modified or updated as required. This document must be approved by the DOE-RL; thereafter, any significant change will require DOE-RL concurrence. Westinghouse Hanford is the DOE-RL operations and engineering contractor at the Hanford Site. Activities associated with this contract (DE-AC06-87RL10930) include operating existing plant facilities, managing defined projects and programs, and planning future enhancements. This document is designed to comply with Section I-13 of the contract by providing a description of Westinghouse Hanford's cost and schedule control systems used in managing the above activities. 5 refs., 22 figs., 1 tab.

Location model of specialized terminals for soybe an exports in Brazil

Directory of Open Access Journals (Sweden)

Alessandra Fraga Dubke

2011-04-01

Full Text Available The purpose of this work is the development of a location model for specialized terminals used as transshipment points in the supply chain of soybeans. The theoretical basis of the study relies on the association of a transshipment model with a multi-commodity, multi-facility capacitated location model. The shipping ports might be seen as specialized terminals that add value to the exported products by transforming raw soy grains into soy oil and soy meal. The proposed model also considers service activities in each terminal and the capacity of the maritime ports. Using representative data from the year 2004, the model is illustrated by a small case study, which considers six points of production in inland Brazil, all served by railways, one maritime port on the north and five on the east coast, and three destination ports in Europe and Asia. The study includes a rough sensitivity analysis regarding volumes, capacities, prices, and transportation costs

Waste management facilities cost information: System cost model product description. Revision 2

International Nuclear Information System (INIS)

Lundeen, A.S.; Hsu, K.M.; Shropshire, D.E.

1996-02-01

In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for DOE wastes. Transportation costs are provided for truck and rail and include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation's generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

Communication Process Between Parents And Children Of Rohingya Refugees To Solve Childrens Traumatic Condition In Termination Medan Northern Sumatra

Directory of Open Access Journals (Sweden)

Imeldarina Ginting

2017-07-01

Full Text Available Staying in the termination environment for a long time as well as very limited facilities is certainly very influential on the physical and psychological development of children Rohingya refugees. Limitations of interaction with the surrounding environment limited financial condition of the family unmet need for continuing education and environmental conditions and shelter that has not been fully adequate. This condition certainly affects the rate of development of refugee children some of whom are very anxious and feel they have no future. Based on the initial observations of refugees both parents and children are very open the main problem is that there is no certainty in the future when they will be placed into a third country and the lack of educational facilities for their children. The average family of refugees has been living in a termination of more than 5 years. Parent-child communication can affect the overall functioning of the family and the psychosocial well-being of the child Shek 2000. Therefore the role of parental communication is needed to overcome traumatic in the Rohingya refugee children. This study aims to find out how the parent communication to overcome the traumatic conditions of children by forming childrens self-concept giving recognition and support and create models. The research method used is descriptive qualitative method by collecting data through interviews to some parents and children in termination both experiencing direct violent conflict and discrimination that happened in during their stay in their country Interpersonal communication between parents and their children in a conflicting situation was interested to be analyzed by using Coordinated Management Meaning Theory because in a conflicting condition parents should set their psychological condition aside as the traumatic victims. The result of the research showed that the function of parents communication with their children could help solve the

Low Speed Wind Tunnel Facility (LSWTF)

Data.gov (United States)

Federal Laboratory Consortium — Description: This facility consists of a large-scale, low-speed open-loop induction wind tunnel which has been modified to house a linear turbine cascade. A 125-hp...

Terminals for the interactive input and editing of bibliographic records on the PDP-11 computer in the CERN Library

International Nuclear Information System (INIS)

Van Praag, A.

1975-01-01

As part of the Library Mechanization Project, special computer terminals have been designed and built for the input and display of a wide range of characters, including Greek letters and mathematical symbols. Each terminal consists of a novel 7-bank keyboard together with two Tektronix 611 storage-tube displays, and there are four terminals connected to a PDP-11/20 computer. After an outline of the hardware for the terminal system, this report gives fuller accounts of the computer interface, display driver, matrix character generator, keyboard, programmable clock, and address comparator. More detailed descriptions of the circuits, the signal formats, and a complete set of schematic diagrams are given as Appendices. (Author)

System description of the Basic MRS System for the FY 1990 Systems Integration Program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Basic MRS System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the Office of Civilian Radioactive Waste Management Office (OCRWM). Two specific systems studies initiated in FY 1990, the Reference System Performance Evaluation and the Aggregate Receipt Rate Study, utilize the information in this document. The Basic MRS System is the current OCRWM reference high-level radioactive wastes repository system concept. It is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes. The Basic MRS System includes a storage-only MRS that provides for a limited amount of commercial spent fuel storage capacity prior to acceptance by the geologic repository for disposal. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. The basic MRS system contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, an MRS facility that provides interim storage wastes accepted from the waste generators, a repository facility that packages the wastes and then emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the waste between these major facilities

Gait adjustments in obstacle crossing, gait initiation and gait termination after a recent lower limb amputation

NARCIS (Netherlands)

Vrieling, Aline H.; van Keeken, Helco G.; Schoppen, Tanneke; Hof, At L.; Otten, Bert; Halbertsma, Jan P. K.; Postema, Klaas

Objective: To describe the adjustments in gait characteristics of obstacle crossing, gait initiation and gait termination that occur in subjects with a recent lower limb amputation during the rehabilitation process. Design: Prospective and descriptive study. Subjects: Fourteen subjects with a recent

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

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-02

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

Overview of NORM and activities by a NORM licensed permanent decontamination and waste processing facility

Energy Technology Data Exchange (ETDEWEB)

Mirro, G.A. [Growth Resources, Inc., Lafayette, LA (United States)

1997-02-01

This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.

Factors associated with utilization of dental services in a long-term care facility: a descriptive cross-sectional study.

Science.gov (United States)

Scannapieco, Frank A; Amin, Summar; Salme, Marc; Tezal, Mine

2017-03-01

To describe factors associated with the utilization of dental services in a long-term care facility (LTCF) in Western New York. A descriptive cross-sectional study reviewed the dental and medical records of residents of an LTCF discharged between January 1, 2008 and December 30, 2012. Information on demographic and health variables at admission was extracted from electronic health records. Information on oral health variables was extracted from patient charts. A total of 2,516 residents were discharged between 2008 and 2012. From those, 259 (10.3%) utilized dental services at least once during their stay. Those who utilized dental services were significantly older at admission (78.5 vs. 82.0 years, p dental services. Dental services appear to be underutilized by residents of LTCF. Significant differences exist in demographic and health variables between residents who utilize these services compared to those who do not. © 2016 Special Care Dentistry Association and Wiley Periodicals, Inc.

Ultraviolet Free Electron Laser Facility preliminary design report

Energy Technology Data Exchange (ETDEWEB)

Ben-Zvi, I. (ed.)

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA).

Ultraviolet Free Electron Laser Facility preliminary design report

International Nuclear Information System (INIS)

Ben-Zvi, I.

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA)

Profiles of facilities used for HTR research and testing

International Nuclear Information System (INIS)

1980-05-01

This report contains a current description of facilities supporting HTR research and development submitted by countries participating in the IWGFR. It has the purpose of providing an overview of the facilities available for use and of the types of experiments that can be conducted therein

National Waste Terminal Storage Program. Progress report, April 1, 1975--September 30, 1976

International Nuclear Information System (INIS)

1976-01-01

This report is divided into two parts: the Management Report and the Technical Report. Section 1 of the Management Report provides a general National Waste Terminal Storage program overview, which includes a summary of the long-range plan. Part II contains the status reports of the technical projects, facility projects, and systems projects

Optimal Conventional and Semi-Natural Treatments for the Upper Yakima Spring Chinook Salmon Supplementation Project, Treatment Definitions and Descriptions, and Biological Specifications for Facility Design, Final Report 1999

International Nuclear Information System (INIS)

Hager, Robert C.; Costello, Ronald J.

1999-01-01

This report describes the Yakima Fisheries Project facilities (Cle Elum Hatchery and acclimation satellites) which provide the mechanism to conduct state-of-the-art research for addressing questions about spring chinook supplementation strategies. The definition, descriptions, and specifications for the Yakima spring chinook supplementation program permit evaluation of alternative fish culture techniques that should yield improved methods and procedures to produce wild-like fish with higher survival that can be used to rebuild depleted spring chinook stocks of the Columbia River Basin. The definition and description of three experimental treatments, Optimal Conventional (OCT), Semi-Natural (SNT), Limited Semi-Natural (LSNT), and the biological specifications for facilities have been completed for the upper Yakima spring chinook salmon stock of the Yakima Fisheries Project. The task was performed by the Biological Specifications Work Group (BSWG) represented by Yakama Indian Nation, Washington Department of Fish and Wildlife, National Marine Fisheries Service, and Bonneville Power Administration. The control and experimental variables of the experimental treatments (OCT, SNT, and LSNT) are described in sufficient detail to assure that the fish culture facilities will be designed and operated as a production scale laboratory to produce and test supplemented upper Yakima spring chinook salmon. Product specifications of the treatment groups are proposed to serve as the generic templates for developing greater specificity for measurements of product attributes. These product specifications will be used to monitor and evaluate treatment effects, with respect to the biological response variables (post release survival, long-term fitness, reproductive success and ecological interactions)

Decommissioning of surplus facilities at ORNL

International Nuclear Information System (INIS)

Myrick, T.E.; Coobs, J.H.

1985-01-01

The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of certain DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 75 facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. This paper describes the scope of the ORNL program and outlines the decommissioning activities currently underway, including a brief description of the decontamination techniques being utilized. 4 refs., 3 figs., 2 tabs

The Termination of Administrative Contracts in the Romanian and French Law

Directory of Open Access Journals (Sweden)

Cătălin-Silviu SĂRARU

2011-11-01

Full Text Available The overall objective of this paper is to present a topic of great interest for the present activity of the public administration that emphasizes the contractual procedures as a vital aspect of entrepreneurial governance. Thus, this article is devoted to a summary of the results of an exploratory research on the conditions for termination of administrative contracts. This study analyzed the conditions under which the administrative contracts can be terminated in the Romanian and French law. The analysis using the comparative method based on a descriptive documentary research, emphasizing the particularities of termination in administrative law in relation to private law. The research is finally recovered by „de lege ferenda” proposals which should, in our opinion, to be reflected in future of the Romanian Administrative Procedure Code. The study is first research in this field in Romania and respond to concrete problems arising in the practice of public administration. The work will have significant implications and for researchers of the administrative phenomenon that in future studies will deepen the problems analyzed here. The work captures doctrinal opinions expressed in comparative law and comes with new legal reasoning to support the research for the juridical institution of the administrative contracts termination.

Operating large controlled thermonuclear fusion research facilities

International Nuclear Information System (INIS)

Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

1987-10-01

The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

Description and Operational Experiences of the Engineering Test Facility - Helium Technology (ETF-HT)

International Nuclear Information System (INIS)

Zhang Zuoyi; Yang Mingde; Bo Hanliang; Duan Riqqiang; Zhu Hongye

2014-01-01

This paper presents the configuration of the Engineering Test Facility - Helium Technology (ETF-HT) and the information of its key components and subsystems, which is located in the Changping campus of Tsinghua University. The ETF-HT facility began to be constructed in Jan. 2009. The main objective of the facility is to test and verify the thermo-hydraulic performance of one full-sized modular unit of HTR-PM helically coiled SG assembly. In the ETF-HT facility, electricity energy is used to heat the loop helium, centrifugal blower is used to circulate the helium medium, and the heat sink is one would-tested SG module. Up to now, except for the tested SG module, preheater and hot gas duct under way of construction, the other components has been installed in situ. Via the temporary connection of the installed components, the preliminary operation of the loop has been carried out to test its performances as can be done, which include the loop leak tightness, blower pneumatic performance and electrical heater at partial thermal load. (author)

National Waste Terminal Storage Program: information management plan. Volume II. Plan description

International Nuclear Information System (INIS)

1977-05-01

A comprehensive information management plan to provide for the systematic processing of large amounts of internally prepared and externally acquired documentation that will accrue to the Office of Waste Isolation (OWI) during the next decade is outlined. The Information Management Plan of the National Waste Terminal Storage (NWTS) Program is based on time proven procedures developed by government and industry for the requirements determination, acquisition, and the administration of documentation. The NWTS Information Management Plan is designed to establish the basis for the planning, development, implemenation, operation and maintenance of the NWTS Information Management System. This plan will help assure that documentation meets required quality standards and that each organization's needs are reflected when soliciting documentation from subcontractors. An example would be the Quality Assurance documentation requirement necessary to comply with eventual NRC licensing regulations. The provisions of the NWTS Information Management Plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to OWI organizations for documentation prepared periodically for external dissemination

Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1990: Twenty-third annual report

International Nuclear Information System (INIS)

Raddatz, C.T.

1993-01-01

This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1990. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1990 annual reports submitted by about 443 licensees indicated that approximately 214,568 individuals were monitored, 110,204 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.19 rem (cSv) and an average measurable dose of about 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,361 individuals completed their employment with one or more of the 443 covered licensees during 1990. Some 77,633 of these individuals terminated from power reactor facilities, and about 11,083 of them were considered to be transient workers who received an average dose of 0.67 rem (cSv)

Implementation of the DYMAC system at the new Los Alamos Plutonium Processing Facility. Phase II report

Energy Technology Data Exchange (ETDEWEB)

Malanify, J.J.; Amsden, D.C.

1982-08-01

The DYnamic Materials ACcountability System - called DYMAC - performs accountability functions at the new Los Alamos Plutonium Processing Facility where it began operation when the facility opened in January 1978. A demonstration program, DYMAC was designed to collect and assess inventory information for safeguards purposes. It accomplishes 75% of its design goals. DYMAC collects information about the physical inventory through deployment of nondestructive assay instrumentation and video terminals throughout the facility. The information resides in a minicomputer where it can be immediately sorted and displayed on the video terminals or produced in printed form. Although the capability now exists to assess the collected data, this portion of the program is not yet implemented. DYMAC in its present form is an excellent tool for process and quality control. The facility operator relies on it exclusively for keeping track of the inventory and for complying with accountability requirements of the US Department of Energy.

Implementation of the DYMAC system at the new Los Alamos Plutonium Processing Facility. Phase II report

International Nuclear Information System (INIS)

Malanify, J.J.; Amsden, D.C.

1982-08-01

The DYnamic Materials ACcountability System - called DYMAC - performs accountability functions at the new Los Alamos Plutonium Processing Facility where it began operation when the facility opened in January 1978. A demonstration program, DYMAC was designed to collect and assess inventory information for safeguards purposes. It accomplishes 75% of its design goals. DYMAC collects information about the physical inventory through deployment of nondestructive assay instrumentation and video terminals throughout the facility. The information resides in a minicomputer where it can be immediately sorted and displayed on the video terminals or produced in printed form. Although the capability now exists to assess the collected data, this portion of the program is not yet implemented. DYMAC in its present form is an excellent tool for process and quality control. The facility operator relies on it exclusively for keeping track of the inventory and for complying with accountability requirements of the US Department of Energy

Methods of designing terminal facilities at the airport "Boryspil" considering external shock dynamic effects

Directory of Open Access Journals (Sweden)

В.Ю. Гирич

2007-01-01

Full Text Available  General procedure of assassination risk estimation is developed. Fast-acting collision of aircraft with building is modeled. The basic mechanisms of building destruction at impact-dynamic influences are described (falling, impact of aircraft. Recommendations, which can be used for building stability estimation at the aircraft impact, are developed. Recommendations for air terminal stability provision against progressing destruction are presented.

ORNL 150 keV neutral beam test facility

International Nuclear Information System (INIS)

Gardner, W.L.; Kim, J.; Menon, M.M.; Schilling, G.

1977-01-01

The 150 keV neutral beam test facility provides for the testing and development of neutral beam injectors and beam systems of the class that will be needed for the Tokamak Fusion Test Reactor (TFTR) and The Next Step (TNS). The test facility can simulate a complete beam line injection system and can provide a wide range of experimental operating conditions. Herein is offered a general description of the facility's capabilities and a discussion of present system performance

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

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

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

2005 dossier: clay. Tome: architecture and management of the geologic disposal facility

International Nuclear Information System (INIS)

2005-01-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the design of a geologic disposal facility for high-level and long-lived radioactive wastes in argilite formations. Content: 1 - approach of the study: goal, main steps of the design study, iterative approach, content; 2 - general description: high-level and long-lived radioactive wastes, purposes of a reversible disposal, geologic context of the Meuse/Haute-Marne site - the Callovo-Oxfordian formation, design principles of the disposal facility architecture, role of the different disposal components; 3 - high-level and long-lived wastes: production scenarios, description of primary containers, inventory model, hypotheses about receipt fluxes of primary containers; 4- disposal containers: B-type waste containers, C-type waste containers, spent fuel disposal containers; 5 - disposal modules: B-type waste disposal modules, C-type waste disposal modules, spent-fuel disposal modules; 6 - overall underground architecture: main safety questions, overall design, dimensioning factors, construction logic and overall exploitation of the facility, dimensioning of galleries, underground architecture adaptation to different scenarios; 7 - boreholes and galleries: general needs, design principles retained, boreholes description, galleries description, building up of boreholes and galleries, durability of facilities, backfilling and sealing up of boreholes and galleries; 8 - surface facilities: general organization, nuclear area, industrial and administrative area, tailings area; 9 - nuclear exploitation means of the facility: receipt of primary containers and preparation of disposal containers, transfer of disposal containers from the surface to the disposal alveoles, setting up of containers inside alveoles; 10 - reversible management of the disposal: step by step disposal process, mastery of disposal behaviour and action capacity, observation and

User's guide to DOE facilities

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

The Department of Energy's research laboratories represent valuable, often unique, resources for university and industrial scientists. It is DOE policy to make these laboratories and facilities available to qualified scientists. The answers to such questions as who are eligible, what and where are the facilities, what is the cost, when can they be used, are given. Data sheets are presented for each facility to provide information such as location, user contact, description of research, etc. A subject index refers to areas of research and equipment available.

Irradiation facilities at the advanced neutron source

International Nuclear Information System (INIS)

West, C.D.

1992-01-01

The Advanced Neutron Source (ANS) is a facility, centered around a new 330MW(f) heavy-water cooled and reflected research reactor, proposed for construction at Oak Ridge. The main scientific justification for the new source is the United States' need for increased capabilities in neutron scattering and other neutron beam research, but the technical objectives of the project also cater for the need to replace the irradiation facilities at the aging High Flux Isotope Reactor and to provide other research capabilities to the scientific community. This document provides a description of the ANS facilities

Cold Vacuum Drying facility sanitary sewage collection system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) sanitary sewage collection system. The sanitary sewage collection system provides collection and storage of effluents and raw sewage from the CVDF to support the cold vacuum drying process. This system is comprised of a sanitary sewage holding tank and pipes for collection and transport of effluents to the sanitary sewage holding tank

Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary[Denmark]; Dekommissionering af Risoes nukleare anlaeg - vurdering af opgaver og omkostninger. Dansk sammenfatning

Energy Technology Data Exchange (ETDEWEB)

Lauridsen, Kurt

2001-02-01

The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

Description of mathematical models and computer programs

International Nuclear Information System (INIS)

1977-01-01

The paper gives a description of mathematical models and computer programs for analysing possible strategies for spent fuel management, with emphasis on economic analysis. The computer programs developed, describe the material flows, facility construction schedules, capital investment schedules and operating costs for the facilities used in managing the spent fuel. The computer programs use a combination of simulation and optimization procedures for the economic analyses. Many of the fuel cycle steps (such as spent fuel discharges, storage at the reactor, and transport to the RFCC) are described in physical and economic terms through simulation modeling, while others (such as reprocessing plant size and commissioning schedules, interim storage facility commissioning schedules etc.) are subjected to economic optimization procedures to determine the approximate lowest-cost plans from among the available feasible alternatives

Effects of wind on background particle concentrations at truck freight terminals.

Science.gov (United States)

Garcia, Ronald; Hart, Jaime E; Davis, Mary E; Reaser, Paul; Natkin, Jonathan; Laden, Francine; Garshick, Eric; Smith, Thomas J

2007-01-01

Truck freight terminals are predominantly located near highways and industrial facilities. This proximity to pollution sources, coupled with meteorological conditions and wind patterns, may affect occupational exposures to particles at these work locations. To understand this process, data from an environmental sampling study of particles at U.S. trucking terminals, along with weather and geographic maps, were analyzed to determine the extent to which the transportation of particles from local pollutant sources elevated observed occupational exposures at these locations. To help identify potential upwind sources, wind direction weighted averages and speed measurements were used to construct wind roses that were superimposed on overhead photos of the terminal and examined for upwind source activity. Statistical tests were performed on these "source" and "nonsource" directions to determine whether there were significant differences in observed particle levels between the two groups. Our results provide evidence that nearby upwind pollution sources significantly elevated background concentrations at only a few of the locations sampled, whereas the majority provided little to no evidence of a significant upwind source effect.

Optimal Conventional and Semi-Natural Treatments for the Upper Yakima Spring Chinook Salmon Supplementation Project; Treatment Definitions and Descriptions and Biological Specifications for Facility Design, 1995-1999 Final Report.

Energy Technology Data Exchange (ETDEWEB)

Hager, Robert C. (Hatchery Operations Consulting); Costello, Ronald J. (Mobrand Biometrics, Inc., Vashon Island, WA)

1999-10-01

This report describes the Yakima Fisheries Project facilities (Cle Elum Hatchery and acclimation satellites) which provide the mechanism to conduct state-of-the-art research for addressing questions about spring chinook supplementation strategies. The definition, descriptions, and specifications for the Yakima spring chinook supplementation program permit evaluation of alternative fish culture techniques that should yield improved methods and procedures to produce wild-like fish with higher survival that can be used to rebuild depleted spring chinook stocks of the Columbia River Basin. The definition and description of three experimental treatments, Optimal Conventional (OCT), Semi-Natural (SNT), Limited Semi-Natural (LSNT), and the biological specifications for facilities have been completed for the upper Yakima spring chinook salmon stock of the Yakima Fisheries Project. The task was performed by the Biological Specifications Work Group (BSWG) represented by Yakama Indian Nation, Washington Department of Fish and Wildlife, National Marine Fisheries Service, and Bonneville Power Administration. The control and experimental variables of the experimental treatments (OCT, SNT, and LSNT) are described in sufficient detail to assure that the fish culture facilities will be designed and operated as a production scale laboratory to produce and test supplemented upper Yakima spring chinook salmon. Product specifications of the treatment groups are proposed to serve as the generic templates for developing greater specificity for measurements of product attributes. These product specifications will be used to monitor and evaluate treatment effects, with respect to the biological response variables (post release survival, long-term fitness, reproductive success and ecological interactions).

Developing a national role description for medical directors in long-term care: survey-based approach.

Science.gov (United States)

Rahim-Jamal, Sherin; Quail, Patrick; Bhaloo, Tajudaullah

2010-01-01

To develop a national role description for medical directors in long-term care (LTC) based on role functions drawn from the literature and the LTC industry. A questionnaire about the role functions identified from the literature was mailed or e-mailed to randomly selected medical directors, directors of care or nursing (DOCs), and administrators in LTC facilities. Long-term care facilities in Canada randomly selected from regional clusters. Medical directors, DOCs, and administrators in LTC facilities; a national advisory group of medical directors from the Long Term Care Medical Directors Association of Canada; and a volunteer group of medical directors. Respondents were asked to indicate, from the list of identified functions, 1) whether medical directors spent any time on each activity; 2) whether medical directors should spend time on each activity; and 3) if medical directors should spend time on an activity, whether the activity was "essential" or "desirable." An overall response rate of 37% was obtained. At least 80% of the respondents from all 3 groups (medical directors, DOCs, and administrators) highlighted 24 functions they deemed to be "essential" or "desirable," which were then included in the role description. In addition, the advisory group expanded the role description to include 5 additional responsibilities from the remaining 18 functions originally identified. A volunteer group of medical directors confirmed the resulting role description. The role description developed as a result of this study brings clarity to the medical director's role in Canadian LTC facilities; the functions outlined are considered important for medical directors to undertake. The role description could be a useful tool in negotiations pertaining to time commitment and expectations of a medical director and fair compensation for services rendered.

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

Osteogenic cell differentiation on H-terminated and O-terminated nanocrystalline diamond films

Directory of Open Access Journals (Sweden)

Liskova J

2015-01-01

Full Text Available Jana Liskova,1 Oleg Babchenko,2 Marian Varga,2 Alexander Kromka,2 Daniel Hadraba,1 Zdenek Svindrych,1 Zuzana Burdikova,1 Lucie Bacakova1 1Institute of Physiology, Academy of Sciences of the Czech Republic, Prague, Czech Republic; 2Institute of Physics, Academy of Sciences of the Czech Republic, Prague, Czech Republic Abstract: Nanocrystalline diamond (NCD films are promising materials for bone implant coatings because of their biocompatibility, chemical resistance, and mechanical hardness. Moreover, NCD wettability can be tailored by grafting specific atoms. The NCD films used in this study were grown on silicon substrates by microwave plasma-enhanced chemical vapor deposition and grafted by hydrogen atoms (H-termination or oxygen atoms (O-termination. Human osteoblast-like Saos-2 cells were used for biological studies on H-terminated and O-terminated NCD films. The adhesion, growth, and subsequent differentiation of the osteoblasts on NCD films were examined, and the extracellular matrix production and composition were quantified. The osteoblasts that had been cultivated on the O-terminated NCD films exhibited a higher growth rate than those grown on the H-terminated NCD films. The mature collagen fibers were detected in Saos-2 cells on both the H-terminated and O-terminated NCD films; however, the quantity of total collagen in the extracellular matrix was higher on the O-terminated NCD films, as were the amounts of calcium deposition and alkaline phosphatase activity. Nevertheless, the expression of genes for osteogenic markers – type I collagen, alkaline phosphatase, and osteocalcin – was either comparable on the H-terminated and O-terminated films or even lower on the O-terminated films. In conclusion, the higher wettability of the O-terminated NCD films is promising for adhesion and growth of osteoblasts. In addition, the O-terminated surface also seems to support the deposition of extracellular matrix proteins and extracellular matrix

Vitrification facility at the West Valley Demonstration Project

International Nuclear Information System (INIS)

DesCamp, V.A.; McMahon, C.L.

1996-07-01

This report is a description of the West Valley Demonstration Project's vitrification facilities from the establishment of the West Valley, NY site as a federal and state cooperative project to the completion of all activities necessary to begin solidification of radioactive waste into glass by vitrification. Topics discussed in this report include the Project's background, high-level radioactive waste consolidation, vitrification process and component testing, facilities design and construction, waste/glass recipe development, integrated facility testing, and readiness activities for radioactive waste processing

304 Concretion facility closure plan

International Nuclear Information System (INIS)

1990-04-01

The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium Zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets in the 304 Concretion Facility, located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Concretion Facility (304 Facility). Clean closure of the 304 Facility is the proposed method for closure of the facility. Justification for this proposal is presented. 15 refs., 22 figs., 4 tabs

Organizational Relationship Termination Competence

DEFF Research Database (Denmark)

Ritter, Thomas; Geersbro, Jens

2011-01-01

termination are found to significantly affect a firm's relationship termination competence. The findings suggest that managers should regard termination as a legitimate option in customer relationship management. In order to decrease the number of unwanted customers, managers must accept termination......Most firms are involved in a number of customer relationships that drain the firm's resources. However, many firms are hesitant to address this problem. This paper investigates customer relationship termination at the organizational level. We develop and analyze the organizational dimensions...... of organizational termination in order to improve our understanding of the management of termination. The impact of these termination dimensions on the percentage of unwanted customers is developed and tested using PLS on data gathered from a cross-sectional survey of more than 800 sales representatives. We find...

Minimizing energy consumption of accelerators and storage ring facilities

International Nuclear Information System (INIS)

The discussion of energy usage falls naturally into three parts. The first is a review of what the problem is, the second is a description of steps that can be taken to conserve energy at existing facilities, and the third is a review of the implications of energy consumption on future facilities

Kitimat LNG terminal

International Nuclear Information System (INIS)

Schmaltz, I.; Boulton, R.

2007-01-01

Kitimat Liquefied Natural Gas (LNG) terminal is a terminal development company owned by Galveston LNG, a privately owned Canadian energy development company. This presentation provided information on Kitimat LNG with particular reference to its terminal located in Bish Cove on the Douglas Channel in British Columbia. This LNG terminal is reported to be the only fully permitted regasification terminal on the west coast of Canada and the United States. The presentation addressed market fundamentals including several graphs, such as world natural gas proved reserves in 2006; LNG supplements to Canadian gas supplies; global LNG demand for 2005-2020; average annual United States LNG imports; and global LNG liquefaction projects. Other market fundamentals were described, including that Kitimat is the only other approved terminal aside from the Costa Azul terminal in Mexico; Kitimat is the only west coast LNG import terminal that connects to midwest and eastern North American markets through existing gas pipelines; LNG producers are looking for destination diversification; and markets and marketers are looking for supply diversification. The authors noted that by 2010, western Canadian gas demand will exceed Californian demand. Other topics that were discussed in the presentation included Canadian natural gas field receipts; unadjusted bitumen production outlook; oil sands gas demand; forward basis fundamentals; and the commercial drivers of the Kitimat LNG terminal. The presentation also discussed the pacific trail pipelines, a partnership between Galveston LNG and Pacific Northern Gas to develop the natural gas transmission line from Kitimat to Summit. The presentation concluded with a discussion of the benefits of Kitimat LNG terminal such as providing access to the largest natural gas markets in the world via major gas transmission lines with spare capacity. figs

1993 baseline solid waste management system description

International Nuclear Information System (INIS)

Armacost, L.L.; Fowler, R.A.; Konynenbelt, H.S.

1994-02-01

Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford's solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions are made, additional data are collected, and assumptions are tested and changed. Out of necessity, this document will also be revised and updated so that a documented system description, which reflects current system planning, is always available for use by engineers and managers. It does not provide any results generated from the many alternatives that will be modeled in the course of analyzing solid waste disposal options; such results will be provided in separate documents

Columbia River: Terminal fisheries research project. 1994 Annual report

Energy Technology Data Exchange (ETDEWEB)

Hirose, P.; Miller, M.; Hill, J.

1996-12-01

Columbia River terminal fisheries have been conducted in Youngs Bay, Oregon, since the early 1960`s targeting coho salmon produced at the state facility on the North Fork Klaskanine River. In 1977 the Clatsop County Economic Development Council`s (CEDC) Fisheries Project began augmenting the Oregon Department of Fish and Wildlife production efforts. Together ODFW and CEDC smolt releases totaled 5,060,000 coho and 411,300 spring chinook in 1993 with most of the releases from the net pen acclimation program. During 1980-82 fall commercial terminal fisheries were conducted adjacent to the mouth of Big Creek in Oregon. All past terminal fisheries were successful in harvesting surplus hatchery fish with minimal impact on nonlocal weak stocks. In 1993 the Northwest Power Planning Council recommended in its` Strategy for Salmon that terminal fishing sites be identified and developed. The Council called on the Bonneville Power Administration to fund a 10-year study to investigate the feasibility of creating and expanding terminal known stock fisheries in the Columbia River Basin. The findings of the initial year of the study are included in this report. The geographic area considered for study extends from Bonneville Dam to the river mouth. The initial year`s work is the beginning of a 2-year research stage to investigate potential sites, salmon stocks, and methodologies; a second 3-year stage will focus on expansion in Youngs Bay and experimental releases into sites with greatest potential; and a final 5-year phase establishing programs at full capacity at all acceptable sites. After ranking all possible sites using five harvest and five rearing criteria, four sites in Oregon (Tongue Point, Blind Slough, Clifton Channel and Wallace Slough) and three in Washington (Deep River, Steamboat Slough and Cathlamet Channel) were chosen for study.

Cold Vacuum Drying Instrument Air System Design Description. System 12

International Nuclear Information System (INIS)

SHAPLEY, B.J.; TRAN, Y.S.

2000-01-01

This system design description (SDD) addresses the instrument air (IA) system of the spent nuclear fuel (SNF). This IA system provides instrument quality air to the Cold Vacuum Drying (CVD) Facility. The IA system is a general service system that supports the operation of the heating, ventilation, and air conditioning (HVAC) system, the process equipment skids, and process instruments in the CVD Facility. The following discussion is limited to the compressor, dryer, piping, and valving that provide the IA as shown in Drawings H-1-82222, Cold Vacuum Drying Facility Mechanical Utilities Compressed and Instrument Air PandID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid PandID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility

Cold Vacuum Drying Instrument Air System Design Description (SYS 12)

Energy Technology Data Exchange (ETDEWEB)

SHAPLEY, B.J.; TRAN, Y.S.

2000-06-05

This system design description (SDD) addresses the instrument air (IA) system of the spent nuclear fuel (SNF). This IA system provides instrument quality air to the Cold Vacuum Drying (CVD) Facility. The IA system is a general service system that supports the operation of the heating, ventilation, and air conditioning (HVAC) system, the process equipment skids, and process instruments in the CVD Facility. The following discussion is limited to the compressor, dryer, piping, and valving that provide the IA as shown in Drawings H-1-82222, Cold Vacuum Drying Facility Mechanical Utilities Compressed & Instrument Air P&ID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid P&ID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility.

Fusion Engineering Device. Volume II. Design description

International Nuclear Information System (INIS)

1981-10-01

This volume summarizes the design of the FED. It includes a description of the major systems and subsystems, the supporting plasma design analysis, a projected device cost and associated construction schedule, and a description of the facilities to house and support the device. This effort represents the culmination of the FY81 studies conducted at the Fusion Engineering Design Center (FEDC). Unique in these design activities has been the collaborative involvement of the Design Center personnel and numerous resource physicists from the fusion community who have made significant contributions in the physics design analysis as well as the physics support of the engineering design of the major FED systems and components

Capabilities of the Power Burst Facility

International Nuclear Information System (INIS)

Spencer, W.A.; Jensen, A.M.; McCardell, R.K.

1982-01-01

The unique and diverse test capabilities of the Power Burst Facility (PBF) are described in this paper. The PBF test reactor, located at the Idaho National Engineering Laboratory, simulates normal, off-normal, and accident operating conditions of light water reactor fuel rods. An overview description is given, with specific detail on design and operating characteristics of the driver core, experiment test loop, fission product detection system, test train assembly facility, and support equipment which make the testing capability of the PBF so versatile

Nuclear facility decommissioning and site remedial actions

International Nuclear Information System (INIS)

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

Nuclear facility decommissioning and site remedial actions

Energy Technology Data Exchange (ETDEWEB)

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

Weapons engineering tritium facility overview

Energy Technology Data Exchange (ETDEWEB)

Najera, Larry [Los Alamos National Laboratory

2011-01-20

Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

77 FR 33805 - Notice of Passenger Facility Charge (PFC) Approvals and Disapprovals

Science.gov (United States)

2012-06-07

... AGENCY: Tri State Airport Authority, Huntington, West Virginia. APPLICATION NUMBER: 12-07-C-00-HTS... equipment. Install perimeter fencing. Rehabilitate terminal building. Rehabilitate taxiway A (west). Access.... Passenger loading bridges. Security exit lane equipment. PFC consulting fees. Brief Description of...

304 Concretion Facility Closure Plan

International Nuclear Information System (INIS)

1991-10-01

The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with Zircaloy-2 and copper silicon allo , uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets (7.5-gal containers) in the 304 Concretion Facility (304 Facility), located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA) and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040 (Ecology 1991). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Facility. The strategy for closure of the 304 Facility is presented in Section 6.0

Exploratory shaft facility preliminary designs - Paradox Basin. Technical report

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Paradox Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Paradox Basin, Utah. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling Method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers is included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references

Earth and environmental science in the 1980's: Part 1: Environmental data systems, supercomputer facilities and networks

Science.gov (United States)

1986-01-01

Overview descriptions of on-line environmental data systems, supercomputer facilities, and networks are presented. Each description addresses the concepts of content, capability, and user access relevant to the point of view of potential utilization by the Earth and environmental science community. The information on similar systems or facilities is presented in parallel fashion to encourage and facilitate intercomparison. In addition, summary sheets are given for each description, and a summary table precedes each section.

Onsite storage facility for low level radwaste

International Nuclear Information System (INIS)

Maxwell, M.G.

1984-01-01

The Tennessee Valley Authority (TVA) has designed and constructed an onsite storage facility for low level radwaste (LLRW) at its Browns Ferry Nuclear Plant in northern Alabama. The paper addresses the function of this facility and provides a complete description of the reinforced concrete storage modules which are the principal structural elements of the facility. The loads and loading combinations for the design of the storage modules are defined to include the foundation design parameters. Other aspects of the modules that are addressed are; the structural roof elements that provide access to the modules, shielding requirements for the LLRW, and tornado missile considerations

Direct Connect Supersonic Combustion Facility (Research Cell 22)

Data.gov (United States)

Federal Laboratory Consortium — Description: RC22 is a continuous-flow, direct-connect supersonic-combustion research facility that is capable of simulating flight conditions from Mach 3.0 to Mach...

Influence of the refractive index core profile on modal scattering of terminated two-dimensional waveguides.

Science.gov (United States)

Koukoutsaki, Panagiota A; Dasyras, Nikolaos F; Tigelis, Ioannis G; Manenkov, Alexander B; Amditis, Angelos J

2007-06-01

We examine the influence of the refractive index core profile on the modal scattering of abruptly terminated slab waveguides. The analysis is based on the integral equation method with accelerating parameters, while for the field description in the waveguide core, an appropriate Lanczos-Fourier expansion is employed. The electric-field distribution on the terminal plane, the reflection and transformation coefficient of the TE guided modes, and the far-field radiation pattern are computed. Numerical results are presented for slab waveguides with step, linear, and parabolic refractive index profiles of the core. Finally, several approximate analytical solutions are derived to study the problem in question and to explain the results obtained.

Cold Vacuum Drying facility crane and hoist system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) crane and hoist system. The overhead crane and hoist system is located in the process bays of the CVDF. It supports the processes required to drain the water and dry the spent nuclear fuel contained in the multi-canister overpacks after they have been removed from the K-Basins. The cranes will also be used to assist maintenance activities within the bays, as required

Safety analysis report for the Mixed Waste Storage Facility and portable storage units at the Idaho National Engineering Laboratory. Revision 4

International Nuclear Information System (INIS)

Peatross, R.

1997-01-01

This revision contains Section 2 only which gives a description of the Mixed Waste Storage Facility (MWSF) and its operations. Described are the facility location, services and utilities, process description and operation, and safety support systems. The MWSF serves as a storage and repackaging facility for low-level mixed waste

The large-scale vented combustion test facility at AECL-WL: description and preliminary test results

International Nuclear Information System (INIS)

Loesel Sitar, J.; Koroll, G.W.; Dewit, W.A.; Bowles, E.M.; Harding, J.; Sabanski, C.L.; Kumar, R.K.

1997-01-01

Implementation of hydrogen mitigation systems in nuclear reactor containments requires testing the effectiveness of the mitigation system, reliability and availability of the hardware, potential consequences of its use and the technical basis for hardware placement, on a meaningful scale. Similarly, the development and validation of containment codes used in nuclear reactor safety analysis require detailed combustion data from medium- and large-scale facilities. A Large-Scale Combustion Test Facility measuring 10 m x 4 m x 3 m (volume, 120 m 3 ) has been constructed and commissioned at Whiteshell Laboratories to perform a wide variety of combustion experiments. The facility is designed to be versatile so that many geometrical configurations can be achieved. The facility incorporates extensive capabilities for instrumentation and high speed data acquisition, on-line gas sampling and analysis. Other features of the facility include operation at elevated temperatures up to 150 degrees C, easy access to the interior, and remote operation. Initial thermodynamic conditions in the facility can be controlled to within 0.1 vol% of constituent gases. The first series of experiments examined vented combustion in the full 120 m 3 -volume configuration with vent areas in the range of 0.56 to 2.24 m 2 . The experiments were performed at ∼27 degrees C and near-atmospheric pressures, with hydrogen concentrations in the range of 8 to 12% by volume. This paper describes the Large-Scale Vented Combustion Test Facility and preliminary results from the first series of experiments. (author)

Experimental data from a full-scale facility investigating radiant and convective terminals

DEFF Research Database (Denmark)

Le Dreau, Jerome; Heiselberg, Per; Jensen, Rasmus Lund

The objective of this technical report is to provide information on the accuracy of the experiments performed in “the Cube” (part I, II and III). Moreover, this report lists the experimental data, which have been monitored in the test facility (part IV). These data are available online and can be...

Occupational radiation exposure at commercial nuclear power reactors and other facilities 1992. Twenty-fifth annual report, Volume 14

International Nuclear Information System (INIS)

Raddatz, C.T.

1993-12-01

This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1992. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10CFR20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10CFR20.408. The 1992 annual reports submitted by about 364 licensees indicated that approximately 204,365 individuals were monitored, 183,927 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measurable dose of about 0.30 (cSv). Termination radiation exposure reports were analyzed to reveal that about 74,566 individuals completed their employment with one or more of the 364 covered licensees during 1992. Some 71,846 of these individuals terminated from power reactor facilities, and about 9,724 of them were considered to be transient workers who received an average dose of 0.50 rem (cSv)

Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1993. Volume 15, Twenty-six annual report

International Nuclear Information System (INIS)

Raddatz, C.T.

1995-01-01

This report the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1993. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1993 annual reports submitted by about 360 licensees indicated that approximately 189,711 individuals were monitored, 169,872 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measured dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 99,749 individuals completed their employment with one or more of the 360 covered licensees during 1993. Some 91,000 of these individuals terminated from power reactor facilities, and about 12,685 of them were considered to be transient workers who received an average dose of 0.49 rem (cSv)

40 CFR 63.11086 - What requirements must I meet if my facility is a bulk gasoline plant?

Science.gov (United States)

2010-07-01

... facility is a bulk gasoline plant? 63.11086 Section 63.11086 Protection of Environment ENVIRONMENTAL... Source Category: Gasoline Distribution Bulk Terminals, Bulk Plants, and Pipeline Facilities Emission... gasoline plant? Each owner or operator of an affected bulk gasoline plant, as defined in § 63.11100, must...

Factors affecting caregiver burden of terminally ill adults in the home setting - A systematic review.

Science.gov (United States)

He Leow, Mabel Qi; Wai Chi Chan, Sally

Background: Terminally ill people have complex physical and psychological needs. As a result, their caregivers may experience high levels of burden, and some caregivers are unable to cope with the burden. Thus, it is important to determine the various factors that may influence caregiver burden, so that healthcare professionals may implement strategies to reduce caregiver burden. In this review, "caregiver burden" was expanded to include "caregiver stress" and "caregiver strain", as the two terms were related to caregiver burden. The objective of this systematic review was to identify the factors that may influence caregiver burden of a terminally ill adult in the home setting. Types of participants: This review considered adult participants (above age 18) who were the main caregivers of a terminally ill adult in the home setting, and providing care for the terminally ill person at the point of participation in the study.Types of intervention: There was no specific intervention of interest for the study.Types of outcomes: The focus of study was the factors that affected caregiver burden of the terminally ill person.Types of studies: Quantitative studies such as randomised controlled trials (RCTs), controlled clinical trials (CCTs), interrupted time series (ITSs), controlled before after designs (CBAs), observational design (cohort, case-control), and descriptive surveys were included in the study. This review was limited to papers in English and Mandarin. A literature search from the inception of the database to October 2010 was conducted using major electronic databases. The databases used were CINAHL, MEDLINE, PsycINFO (Ovid), Scopus, SpringerLink, ScienceDirect, Web of Science, Mosby's Nursing Consult, Mednar: Deep web medical search, Proquest Dissertations and Theses and China Journal Net.Methodological quality: The quality of the potential studies was assessed by two independent reviewers using the critical appraisal checklists for descriptive/case studies

Data collection, validation, and description for the Oak Ridge nuclear facilities mortality study

International Nuclear Information System (INIS)

Watkins, J.P.; Reagan, J.L.; Cragle, D.L.; West, C.M.; Tankersley, W.G.; Crawford-Brown, D.J.

1995-01-01

To investigate the long-term health effects of protracted occupational exposure to low levels of ionizing radiation, a mortality study was initiated by pooling data for 118,588 workers hired between 1943 and 1982, at three Department of Energy (DOE) facilities in Oak Ridge, Tennessee, with follow-up through 1984. Topics for this discussion will include issues involving the collection and validation of data for individuals in the study cohort, and characteristics of their demographic and radiation exposure data. Since the data were compiled between the late 1960s and the present under the direction of several principal investigators, it was essential to verify data precision and to understand how exposure data were generated prior to beginning any analysis. A stratified random sample of workers in the cohort was chosen for verification of their computerized data as it appeared in the database. Original source documents were reviewed to verify demographic data, as well as internal and external radiation exposure data. Extensive effort was expended to document the personal radiation monitoring policies and types of dosimeters used at each facility over the 42 years included in the study. Characteristics of internal and external exposure data by facility and year were examined by graphical methods with the intent of combining these monitoring data over time and across facilities

Readiness of health facilities to deliver safe male circumcision services in Tanzania: a descriptive study

Directory of Open Access Journals (Sweden)

Frank Felix Mosha

2013-03-01

Full Text Available Assessing the readiness of health facilities to deliver safe male circumcision services is more important in sub-Saharan Africa because of the inadequacy state of health facilities in many ways. The World Health Organization recommends that only facilities equipped with available trained staff, capable to perform at least minor surgery, able to offer minimum MC package and appropriate equipment for resuscitation, and compliant with requirements for sterilization and infection control should be allowed to deliver safe circumcision services. A cross-sectional study using quantitative data collection technique was conducted to assess the readiness of the health facilities to deliver safe circumcision services in selected districts of Tanzania. All hospitals, health centres and 30% of all dispensaries in these districts were selected to participate in the study. Face-toface questionnaires were administered to the heads of the health facilities and to health practitioners. Overall, 49/69 (59% of the facilities visited provided circumcision services and only 46/203 (24% of the health practitioners performed circumcision procedures. These were mainly assistant medical officers and clinical officers. The vast majority – 190/203 (95% – of the health practitioners require additional training prior to providing circumcision services. Most facilities – 63/69 (91% – had all basic supplies (gloves, basin, chlorine and waste disposal necessary for infection prevention, 44/69 (65% provided condoms, HIV counselling and testing, and sexuallytransmitted infections services, while 62/69 (90% had the capability to perform at least minor surgery. However, only 25/69 (36% and 15/69 (22% of the facilities had functioning sterilization equipment and appropriate resuscitation equipment, respectively. There is readiness for roll out of circumcision services; however, more practitioners need to be trained on circumcision procedures, demand forecasting

Baseline descriptions for LWR spent fuel storage, handling, and transportation

Energy Technology Data Exchange (ETDEWEB)

Moyer, J.W.; Sonnier, C.S.

1978-04-01

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables.

Baseline descriptions for LWR spent fuel storage, handling, and transportation

International Nuclear Information System (INIS)

Moyer, J.W.; Sonnier, C.S.

1978-04-01

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables

LNG REGASIFICATION TERMINALS ACCESS CAPACITY ANALYSIS FOR SECURITY OF EUROPEAN NATURAL GAS SUPPLY

Directory of Open Access Journals (Sweden)

Matija Veselić

2011-12-01

Full Text Available Increasing natural gas consumption, declining North Sea gas reserves, increased production costs and the deregulation of European gas and electricity markets have all combined to create new opportunities for LNG in Europe. In these circumstances, LNG represents an opportunity for many European countries to diversify their natural gas supply, while decreasing their dependence on Russian natural gas import at the same time. The largest exporters of LNG to Europe are Qatar, Algeria, Nigeria, Trinidad & Tobago, Egypt and Oman. Spain, Great Britain and France are the largest European importers of LNG. Spain has six LNG regasification terminals, followed by four in Great Britain, three in France, two in Italy and Turkey and finally Greece and Portugal with one terminal each. New LNG regasification terminals are currently under construction in Italy, Spain, Sweden and Netherlands. In addition, more than 30 new LNG terminal projects have been proposed around Europe. Italy plans to construct as many as 10 new regasification terminals, due to the strong orientation of its national energy policy towards LNG. Many European countries are strongly considering participating in the LNG chain for the first time, namely Albania, Cyprus, Ireland, Lithuania, Germany, Poland, Romania, Ukraine and Croatia. This paper focuses on a specific aspect of the LNG supply chain: the import facility (the paper is published in Croatian.

Recent progress in ignition fusion research on the National Ignition Facility

International Nuclear Information System (INIS)

Leeper, Ramon J.

2011-01-01

This paper will review the ignition fusion research program that is currently being carried out on the National Ignition Facility (NIF) located at Lawrence Livermore National Laboratory. This work is being conducted under the auspices of the National Ignition Campaign (NIC) that is a broad collaboration of national laboratories and universities that together have developed a detailed research plan whose goal is ignition in the laboratory. The paper will begin with a description of the NIF facility and associated experimental facilities. The paper will then focus on the ignition target and hohlraum designs that will be tested in the first ignition attempts on NIF. The next topic to be introduced will be a description of the diagnostic suite that has been developed for the initial ignition experiments on NIF. The paper will then describe the experimental results that were obtained in experiments conducted during the fall of 2009 on NIF. Finally, the paper will end with a description of the detailed experimental plans that have been developed for the first ignition campaign that will begin later this year. (author)

Justification of the project a network of freight terminals unitized cargo

Directory of Open Access Journals (Sweden)

Ilesaliev D.I.

2016-12-01

Full Text Available In this paper we consider the question of Uzbekistan in promoting the development of international transport in supply chains. The development of transport infrastructure to ensure timely delivery of goods is one of the main tasks in supply chain management. The aim is to study of the project network terminal unitized cargo Uzbekistan in supply chains. Methods the study is based on analysis of existing methods and techniques of Russian scientists in the field of place-ment of objects. The method of searching the most rational location of logistics facility in the supply chain. Also pre-justified the project network terminal unitized cargo in Uzbekistan. Given the state of the problems and prospects of transport logistics of Uzbekistan, the developed method can be used by experts when performing the supporting calcula-tions location of logistic objects.

A meta-analytic review of two modes of learning and the description-experience gap.

Science.gov (United States)

Wulff, Dirk U; Mergenthaler-Canseco, Max; Hertwig, Ralph

2018-02-01

People can learn about the probabilistic consequences of their actions in two ways: One is by consulting descriptions of an action's consequences and probabilities (e.g., reading up on a medication's side effects). The other is by personally experiencing the probabilistic consequences of an action (e.g., beta testing software). In principle, people taking each route can reach analogous states of knowledge and consequently make analogous decisions. In the last dozen years, however, research has demonstrated systematic discrepancies between description- and experienced-based choices. This description-experience gap has been attributed to factors including reliance on a small set of experience, the impact of recency, and different weighting of probability information in the two decision types. In this meta-analysis focusing on studies using the sampling paradigm of decisions from experience, we evaluated these and other determinants of the decision-experience gap by reference to more than 70,000 choices made by more than 6,000 participants. We found, first, a robust description-experience gap but also a key moderator, namely, problem structure. Second, the largest determinant of the gap was reliance on small samples and the associated sampling error: free to terminate search, individuals explored too little to experience all possible outcomes. Third, the gap persisted when sampling error was basically eliminated, suggesting other determinants. Fourth, the occurrence of recency was contingent on decision makers' autonomy to terminate search, consistent with the notion of optional stopping. Finally, we found indications of different probability weighting in decisions from experience versus decisions from description when the problem structure involved a risky and a safe option. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

Design cost scoping studies. Nevada Test Site Terminal Waste Storage Program, Subtask 1.3: facility hardening studies

International Nuclear Information System (INIS)

Yanev, P.I.; Owen, G.N.

1978-04-01

As part of a program being conducted by the U.S. Department of Energy, Nevada Operations Office, to determine the feasibility of establishing a terminal waste storage repository at the Nevada Test Site, URS/John A. Blume and Associates, Engineers, made approximate determinations of the additional costs required to provide protection of structures against seismic forces. A preliminary estimate is presented of the added costs required to harden the surface structures, underground tunnels and storage rooms, and vertical shafts of the repository against ground motion caused by earthquakes and underground nuclear explosions (UNEs). The conceptual design of all of the structures was adapted from proposed bedded-salt waste-isolation repositories. Added costs for hardening were calculated for repositories in three candidate geological materials (Eleana argillite, Climax Stock granite, and Jackass Flats tuff) for several assumed peak ground accelerations caused by earthquakes (0.3g, 0.5g, and 0.7g) and by UNEs (0.5g, 0.7g, and 1.0g). Hardening procedures to protect the tunnels, storage rooms, and shafts against incremental seismic loadings were developed from (1) qualitative considerations of analytically determined seismic stresses and (2) engineering evaluations of the dynamic response of the rock mass and the tunnel support systems. The added costs for seismic hardening of the surface structures were found to be less than 1% of the estimated construction cost of the surface structures. For the underground structures, essentially no hardening was required for peak ground accelerations up to 0.3g; however, added costs became significant at 0.5g, with a possible increase in structural costs for the underground facilities of as much as 35% at 1.0g

Cold Vacuum Drying facility personnel monitoring system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) instrument air (IA) system that provides instrument quality air to the CVDF. The IA system provides the instrument quality air used in the process, HVAC, and HVAC instruments. The IA system provides the process skids with air to aid in the purging of the annulus of the transport cask. The IA system provides air for the solenoid-operated valves and damper position controls for isolation, volume, and backdraft in the HVAC system. The IA system provides air for monitoring and control of the HVAC system, process instruments, gas-operated valves, and solenoid-operated instruments. The IA system also delivers air for operating hand tools in each of the process bays

Legal questions concerning the termination of spent fuel element reprocessing

International Nuclear Information System (INIS)

John, Michele

2005-01-01

The thesis on legal aspects of the terminated spent fuel reprocessing in Germany is based on the legislation, jurisdiction and literature until January 2004. The five chapters cover the following topics: description of the problem; reprocessing of spent fuel elements in foreign countries - practical and legal aspects; operators' responsibilities according to the atomic law with respect to the reprocessing of Geman spent fuel elements in foreign countries; compatibility of the prohibition of Geman spent fuel element reprocessing in foreign countries with international law, European law and German constitutional law; results of the evaluation

Delivering information: a descriptive study of Australian women's information needs for decision-making about birth facility.

Science.gov (United States)

Thompson, Rachel; Wojcieszek, Aleena M

2012-06-18

Little information is known about what information women want when choosing a birth facility. The objective of this study was to inform the development of a consumer decision support tool about birth facility by identifying the information needs of maternity care consumers in Queensland, Australia. Participants were 146 women residing in both urban and rural areas of Queensland, Australia who were pregnant and/or had recently given birth. A cross-sectional survey was administered in which participants were asked to rate the importance of 42 information items to their decision-making about birth facility. Participants could also provide up to ten additional information items of interest in an open-ended question. On average, participants rated 30 of the 42 information items as important to decision-making about birth facility. While the majority of information items were valued by most participants, those related to policies about support people, other women's recommendations about the facility, freedom to choose one's preferred position during labour and birth, the aesthetic quality of the facility, and access to on-site neonatal intensive care were particularly widely valued. Additional items of interest frequently focused on postnatal care and support, policies related to medical intervention, and access to water immersion. The women surveyed had significant and diverse information needs for decision-making about birth facility. These findings have immediate applications for the development of decision support tools about birth facility, and highlight the need for tools which provide a large volume of information in an accessible and user-friendly format. These findings may also be used to guide communication and information-sharing by care providers involved in counselling pregnant women and families about their options for birth facility or providing referrals to birth facilities.

Meteorological instrumentation for nuclear facilities

International Nuclear Information System (INIS)

Costa, A.C.L. da.

1983-01-01

The main requirements of regulatory agencies, concerning the meteorological instrumentation needed for the licensing of nuclear facilities are discussed. A description is made of the operational principles of sensors for the various meteorological parameters and associated electronic systems. An analysis of the problems associated with grounding of a typical meteorological station is presented. (Author) [pt

ATR National Scientific User Facility 2015 Annual Report

Energy Technology Data Exchange (ETDEWEB)

Robertson, Sarah [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kennedy, J. Rory [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ogden, Dan [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cole, Jim [Idaho National Lab. (INL), Idaho Falls, ID (United States); Knight, Collin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Teysseyre, Sebastien [Idaho National Lab. (INL), Idaho Falls, ID (United States); Benson, Jeff [Idaho National Lab. (INL), Idaho Falls, ID (United States); Heidrich, Brenden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Jackson, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bean, Lindy [Idaho National Lab. (INL), Idaho Falls, ID (United States); Soelberg, Renae [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

This is the 2015 Annual Report for the Nuclear Science User Facility. This report includes information on university-run research projects along with a description of the program and the capabilities offered researchers.

Field and numerical descriptions of fracture geometries and terminations in chalk containing chert layers and inclusions; implications for groundwater flow in Danish chalk aquifers

Science.gov (United States)

Seyum, S.

2017-12-01

This study is a description of the fracture distribution in laterally discontinuous chalk and chert layers, with an investigation on how fracture lengths and apertures vary as a function of applied stresses, material properties, and interface properties. Natural fractures intersect laterally extensive, discontinuous, chalk-chert material interfaces in 62 million-year old to 72 million-year old Chalk Group formations exposed at Stevns Klint, Denmark. Approximately one-third of Denmark's fresh water use is from chalk and limestone regional aquifers of the Chalk Group formations, where rock permeability is dominantly a function of open fracture connectivities. Fractured, centimeter- to decimeter-thick chert layers and inclusions (101 GPa elastic stiffness) are interlayered with fractured, meter-thick chalk layers (100 GPa elastic stiffness). Fractures are observed to terminate against and cross chalk-chert interfaces, affecting the vertical flow of water and pollutants between aquifers. The discontinuous and variably thin nature of chert layers at Stevns Klint effectively merges adjacent fracture-confining layers of chalk along discrete position intervals, resulting in lateral variability of fracture spacing. Finite element numerical models are designed to describe fracture interactions with stiff, chert inclusions of various shapes, thicknesses, widths, orientations, and interface friction and fracture toughness values. The models are two-dimensional with isotropic, continuous material in plane strain and uniformly applied remote principal stresses. These characteristics are chosen based on interpretations of the petrophysics of chalk and chert, the burial history of the rock, and the scale of investigation near fracture tips relative to grain sizes. The result are value ranges for relative stiffness contrasts, applied stresses, and material interface conditions that would cause fractures to cross, terminate at, or form along chalk-chert interfaces, with emphasis on

75 FR 18850 - National Protection and Programs Directorate; Chemical Facility Anti-Terrorism Standards...

Science.gov (United States)

2010-04-13

... Directorate; Chemical Facility Anti-Terrorism Standards Personnel Surety Program AGENCY: National Protection...-terrorism Vulnerability Information (CVI), Sensitive Security Information (SSI), or Protected Critical... . SUPPLEMENTARY INFORMATION: Program Description The Chemical Facility Anti-Terrorism Standards (CFATS), 6 CFR...

CONTAINER TERMINALS IN EUROPE

Directory of Open Access Journals (Sweden)

Bart W. WIEGMANS

2001-01-01

Full Text Available This paper aims to address the linkage between logistics (in particular, the management of marketing channel flows and transport markets, while also the interaction between these two markets and intermodal container terminals is analysed. The marketing channel theory is used to describe all relevant actors and flows that run through marketing channels, starting with customer needs and ending with customer satisfaction. Porter's theory of competitive advantages is used to review competitive forces in both markets. Finally, a competitor analysis is performed for the logistics and transport market. These theories are applied so as to be able to determine the competitive position of intermodal container terminals with a view to the management of marketing channel flows and the physical transport of freight flows. Hence, the central question of this paper is: Which markets are served by intermodal container terminals and with whom are they competing? At present, neither the maritime container terminals nor the continental container terminals appear to have a significant influence in the logistics service market; they concentrate mainly on the physical movement of containers (transshipment. Furthermore, maritime container terminals and continental container terminals are not dominant players in the transport service market. Our conclusion is that continental terminals are predominantly competing with unimodal road transport, with neighbouring continental terminals and with barge transport companies.

A description of the Canadian irradiation-research facility proposed to replace the NRU reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, A G; Lidstone, R F; Bishop, W E; Talbot, E F; McIlwain, H [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-12-31

To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (CANada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities, and support facilities. At a nominal reactor power of 40 MW{sub t}, the IRF will generate powers up to 1 MW in natural-uranium CANDU bundles, fast-neutron fluxes up to 1.4 x 10{sup 18} n{center_dot}m{sup -2}{center_dot}s{sup -1} in Zr-alloy specimens, and thermal-neutron fluxes matching those available to the NRU beam tubes. (author). 9 refs., 5 tabs., 2 figs.

The Radiological Research Accelerator Facility. Progress report, December 1, 1993--November 30, 1994

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1994-04-01

This document begins with a general description of the facility to include historical and up-to-date aspects of design and operation. A user's guide and a review of research using the facility follows. Next the accelerator utilization and operation and the development of the facilities is given. Personnel currently working at the facility are listed. Lastly, recent publications and literature cited are presented

Safety Report within the licence application for the siting of a radioactive waste repository/disposal facility

International Nuclear Information System (INIS)

Horyna, J.; Sinaglova, R.

2004-01-01

The initial safety specification report, which is submitted to the licensing authority as one of the application documents, is the basic document assessing the planned repository/disposal facility with respect to the suitability of the chosen site for this purpose. The following topics are covered: General information; Description and evidence of suitability of the site chosen; Description and tentative assessment of the repository/disposal facility design; Tentative assessment of impacts of running the facility on the employees, general public and environment (radionuclide inventory, transport routes, radionuclide release in normal, abnormal and emergency situations); Proposed concept of repository/disposal facility shutdown; and Assessment of quality assurance in the site selection, in preparatory work for the construction of the facility and in the subsequent stages. (P.A.)

The SWARF high energy flash X-ray facility

International Nuclear Information System (INIS)

Gilbert, J.F.; Dove, E.W.D.

1976-06-01

A description is presented of the SWARF flash radiography facility at AWRE Foulness, which is stated to be the most powerful flash x-ray system available, in the U.K. The machine consists essentially of a Marx generator, a coaxial Blumlein system and an x-ray tube. The voltage output from the Marx generator (about 2.5 MV from an 80 kV input) is applied to a large re-entrant Blumlein pulse-forming line. Near maximum voltage, an adjustable oil switch short-circuits one end of the Blumlein generator and so applies a square voltage pulse of 65 ns duration to the x-ray tube. The x-rays are produced from a tantalum target which forms the anode of a vacuum field emission diode. The facility consists of two field machines positioned so that radiographs can be obtained from different angles. The description is given under the following heads: modus operandi; constructional details; oil installation; electrical details; commissioning, calibration and electrical data; flash radiography in explosives research; operational control of facility, film packs; radiographic results; further developments; overall performance. (U.K.)

Fiber Fabrication Facility for Non-Oxide and Specialty Glasses

Data.gov (United States)

Federal Laboratory Consortium — FUNCTION: Unique facility for the research, development, and fabrication of non-oxide and specialty glasses and fibers in support of Navy/DoD programs.DESCRIPTION:...

Energy Systems Test Area (ESTA). Power Systems Test Facilities

Science.gov (United States)

Situ, Cindy H.

2010-01-01

This viewgraph presentation provides a detailed description of the Johnson Space Center's Power Systems Facility located in the Energy Systems Test Area (ESTA). Facilities and the resources used to support power and battery systems testing are also shown. The contents include: 1) Power Testing; 2) Power Test Equipment Capabilities Summary; 3) Source/Load; 4) Battery Facilities; 5) Battery Test Equipment Capabilities Summary; 6) Battery Testing; 7) Performance Test Equipment; 8) Battery Test Environments; 9) Battery Abuse Chambers; 10) Battery Abuse Capabilities; and 11) Battery Test Area Resources.

Exploratory shaft facility preliminary designs - Gulf Interior Region salt domes

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Gulf Interior Region, is to provide a description of the preliminary design for an Exploratory Shaft Facility on the Richton Dome, Mississippi. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description and Construction Cost Estimate

Simulation evaluation of TIMER, a time-based, terminal air traffic, flow-management concept

Science.gov (United States)

Credeur, Leonard; Capron, William R.

1989-01-01

A description of a time-based, extended terminal area ATC concept called Traffic Intelligence for the Management of Efficient Runway scheduling (TIMER) and the results of a fast-time evaluation are presented. The TIMER concept is intended to bridge the gap between today's ATC system and a future automated time-based ATC system. The TIMER concept integrates en route metering, fuel-efficient cruise and profile descents, terminal time-based sequencing and spacing together with computer-generated controller aids, to improve delivery precision for fuller use of runway capacity. Simulation results identify and show the effects and interactions of such key variables as horizon of control location, delivery time error at both the metering fix and runway threshold, aircraft separation requirements, delay discounting, wind, aircraft heading and speed errors, and knowledge of final approach speed.

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.

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.

DOE research and development and field facilities

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

Demonstration of safety of decommissioning of facilities using radioactive material

International Nuclear Information System (INIS)

Batandjieva, Borislava; O'Donnell, Patricio

2008-01-01

Full text:The development of nuclear industry worldwide in the recent years has particular impact on the approach of operators, regulators and interested parties to the implementation of the final phases (decommissioning) of all facilities that use radioactive material (from nuclear power plants, fuel fabrication facilities, research reactors to small research or medical laboratories). Decommissioning is becoming an increasingly important activity for two main reasons - termination of the practice in a safe manner with the view to use the facility or the site for other purposes, or termination of the practice and reuse the facility or site for new built nuclear facilities. The latter is of special relevance to multi-facility sites where for example new nuclear power plants and envisaged. However, limited countries have the adequate legal and regulatory framework, and experience necessary for decommissioning. In order to respond to this challenge of the nuclear industry and assist Member States in the adequate planning, conduct and termination of decommissioning of wide range of facilities, over the last decade the IAEA has implemented and initiated several projects in this field. One of the main focuses of this assistance to operators, regulators and specialists involved in decommissioning is the evaluation and demonstration of safety of decommissioning. This importance of these Agency activities was also highlighted in the International Action Plan on Decommissioning, during the second Joint Convention meeting in 2006 and the International Conference on Lessons Learned from Decommissioning in Athens in 2006. The IAEA has been providing technical support to its Member States in this field through several mechanisms: (1) the establishment of a framework of safety standards on decommissioning and development of a supporting technical documents; (2) the establishment of an international peer review mechanism for decommissioning; (3) the technical cooperation projects

Termination of Safeguards on ULWBR Material

International Nuclear Information System (INIS)

Ivan R. Thomas; Ernest L. Laible

2008-01-01

The Department of Energy (DOE), Office of Environmental Management, has approved the disposition of 31 metric tons of Unirradiated Light Water Breeder Reactor (ULWBR) material in canisters stored within dry wells of the Underground Fuel Storage Facility at the Idaho Nuclear Technology and Engineering Center (INTEC). This unirradiated material consists primarily of ceramic pellets of thorium oxide in stainless steel cladding, but it also contains 300 kilograms of uranium that is 98 wt% U-233. The ULWBR material was not processed at the INTEC because it was incompatible with prior chemical separation schemes. Other economical recovery options have not been identified, and expressions of interest for consolidating the material with existing projects at other DOE sites have not been received. The U-233 could be used for producing the medical isotope Actinium-225, but the proof-of-principle demonstration and follow-on pilot program have not been developed to the point of requiring production quantities of U-233. Consequently, the selected disposition of the ULWBR material was burial as Low Level Waste at the Nevada Test Site (NTS), which required terminating safeguards controls for the contained Category II quantity of Attractiveness Level D special nuclear material (SNM). The requested termination followed the twelve point evaluation criteria of the Historical Defense Program Discard Guidance and included a security analysis for evaluating the risks of theft, diversion, and radiological sabotage associated with the material. Continuity of knowledge in the book inventory was assured by documenting that the original shipper's measurements accurately reflected the quantities of materials received and that the ULWBR materials had remained under adequate physical protection and had been subject to periodic physical inventories. The method selected for substantiating the book values as the basis for terminating safeguards was the nondestructive assay used during physical

Telidon Videotex presentation level protocol: Augmented picture description instructions

Science.gov (United States)

Obrien, C. D.; Brown, H. G.; Smirle, J. C.; Lum, Y. F.; Kukulka, J. Z.; Kwan, A.

1982-02-01

The Telidon Videotex system is a method by which graphic and textual information and transactional services can be accessed from information sources by the general public. In order to transmit information to a Telidon terminal at a minimum bandwidth, and in a manner independent of the type of communications channel, a coding scheme was devised which permits the encoding of a picture into the geometric drawing elements which compose it. These picture description instructions are an alpha geometric coding model and are based on the primitives of POINT, LINE, ARC, RECTANGLE, POLYGON, and INCREMENT. Text is encoded as (ASCII) characters along with a supplementary table of accents and special characters. A mosaic shape table is included for compatibility. A detailed specification of the coding scheme and a description of the principles which make it independent of communications channel and display hardware are provided.

Third party access to LNG terminals. GIIGNL - Commercial Study Group Topic 8

International Nuclear Information System (INIS)

2012-11-01

This report has been elaborated in the context of the GIIGNL Commercial Study Group (CSG) activities, which include as one of its topics the 'Third Party Access to LNG terminals' (Topic 8), led by Enagas. The 2010 edition is the third update to the report presented during the meeting of the GIIGNL Commercial Study Group in Tokyo, Japan, in September 2007. - Section 1 includes a review of the regulatory TPA regimes of LNG terminals in operation in Europe. The existing regime in each country, or for each terminal, is reviewed following a number of subsections. Each subsection follows the same structure in order to better understand the different arrangements and facilitate comparisons. - Section 2 shows data on effective usage and TPA access to each LNG terminal since 2000. Three main data are shown where available: number of cargoes delivered, volumes unloaded / sent-out, and the part of these cargoes/volumes that correspond to third parties. - Section 3 includes a tariff comparison for TPA to LNG terminals in Europe, taking into account the terms and conditions in force as of July 2010. - A description of the regulatory situation in the US in Sections 4. Access conditions to the three terminals under regulated TPA have been included for the first time: Lake Charles, Cove Point and Elba Island. An overview of Mexico and Canada is also reported. - An overview of the regulatory situation in Japan is provided in Section 5. The information required for the elaboration of this report has been collected from official web sites (LNG operators, regulatory authorities and industry associations), public reports and industry and statistical data Enagas deems to be reliable. For the adoption of certain hypothesis in Section 3 Enagas has also relied in information directly provided by operators

The proposed irradiation facility and applications

International Nuclear Information System (INIS)

Singson, C.C.; Navarro, Q.O.

As early as 1972, the Philippine Atomic Energy Commission proposed the setting up of a radiation facility for the sterilization of medical products. A result of a market survey with the assistance of an IAEA expert was conducted to determine the market potential for such venture. With the Food Terminal, Inc. (FTI) a government agro-industrial fair which explored the economic benefits of project, encouraging results have been obtained with finances from FAO and IAEA. The proposed pilot plant will serve as a multi purpose facility for the sterilization of medical and laboratory products, irradiation of food and agricultural produce and manufacture of wood plastic compositions for the textile and furniture industries. With the benefits derived from the said project, it is hoped that its early installation be pushed through. (author)

ATR National Scientific User Facility 2013 Annual Report

Energy Technology Data Exchange (ETDEWEB)

Ulrich, Julie A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Robertson, Sarah [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

This is the 2013 Annual Report for the Advanced Test Reactor National Scientific User Facility. This report includes information on university-run research projects along with a description of the program and the capabilities offered researchers.

Holifield Heavy-Ion Research Facility at Oak Ridge

International Nuclear Information System (INIS)

Jones, C.M.

1977-01-01

A new heavy-ion accelerator facility is now under construction at the Oak Ridge National Laboratory. A brief description of the scope and schedule of this project is given, and the new large tandem accelerator, which will be a major element of the facility is discussed in some detail. Several studies which have been made or are in progress in Oak Ridge in preparation for operation of the tandem accelerator are briefly described

The single-angle neutron scattering facility at Pelindaba

International Nuclear Information System (INIS)

Hofmeyr, C.; Mayer, R.M.; Tillwick, D.L.; Starkey, J.R.

1978-05-01

The small-angle neutron scattering facility at the SAFARI-1 reactor is described in detail, and with reference to theoretical and practical design considerations. Inexpensive copper microwave guides used as a guide-pipe for slow neutrons provided the basis for a useful though comparatively simple facility. The neutron-spectrum characteristics of the final facility in different configurations of the guide-pipe (both S and single-curved) agree wel with expected values based on results obtained with a test facility. The design, construction, installation and alignment of various components of the facility are outlined, as well as intensity optimisation. A general description is given of experimental procedures and data-aquisition electronics for the four-position sample holder and counter array of up to 18 3 He detectors and a beam monitor [af

Liquid Metal Fast Breeder Reactor Program: Argonne facilities

International Nuclear Information System (INIS)

Stephens, S.V.

1976-09-01

The objective of the document is to present in one volume an overview of the Argonne National Laboratory test facilities involved in the conduct of the national LMFBR research and development program. Existing facilities and those under construction or authorized as of September 1976 are described. Each profile presents brief descriptions of the overall facility and its test area and data relating to its experimental and testing capability. The volume is divided into two sections: Argonne-East and Argonne-West. Introductory material for each section includes site and facility maps. The profiles are arranged alphabetically by title according to their respective locations at Argonne-East or Argonne-West. A glossary of acronyms and letter designations in common usage to describe organizations, reactor and test facilities, components, etc., involved in the LMFBR program is appended

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

Energy Technology Data Exchange (ETDEWEB)

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1987-09-01

The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

International Nuclear Information System (INIS)

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1987-09-01

The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations

77 FR 70174 - Waterway Suitability Assessment for Expansion of Liquefied Gas Terminals; Houston and Texas City, TX

Science.gov (United States)

2012-11-23

... Assessment for Expansion of Liquefied Gas Terminals; Houston and Texas City, TX AGENCY: Coast Guard, DHS... Assessment to the Coast Guard Captain of the Port, Sector Houston-Galveston regarding the company's proposed expansion of its Liquefied Hazardous Gas (LHG) facilities in Houston and Texas City, Texas, and increased...

Investigating walking environments in and around assisted living facilities: a facility visit study.

Science.gov (United States)

Lu, Zhipeng

2010-01-01

This study explores assisted living residents' walking behaviors, locations where residents prefer to walk, and walking environments in and around assisted living facilities. Regular walking is beneficial to older adults' physical and psychological health. Yet frail older residents in assisted living are usually too sedentary to achieve these benefits. The physical environment plays an important role in promoting physical activity. However, there is little research exploring this relationship in assisted living settings. The researcher visited 34 assisted living facilities in a major Texas city. Methods included walk-through observation with the Assisted Living Facility Walking Environment Checklist, and interviews with administrators by open- and close-ended questions. The data from 26 facilities were analyzed using descriptive statistics (for quantitative data) and content analysis (for qualitative data). The results indicate that (a) residents were walking both indoors and outdoors for exercise or other purposes (e.g., going to destinations); (b) assisted living facility planning and design details-such as neighborhood sidewalk conditions, facility site selection, availability of seating, walking path configuration (e.g., looped/nonlooped path), amount of shading along the path, presence of handrails, existence of signage, etc.-may influence residents' walking behaviors; and (c) current assisted living facilities need improvement in all aspects to make their environments more walkable for residents. Findings of the study provide recommendations for assisted living facilities to improve the walkability of environments and to create environmental interventions to promote regular walking among their residents. This study also implies several directions for future research.

Survey and assessment of radioactive waste management facilities in the United States. Section 2.5. Air-cooled vault storage facilities

International Nuclear Information System (INIS)

1986-01-01

There are two basic types of air-cooled vaults for the storage of spent nuclear fuel or vitrified HLRW. The two types, differentiated by the method of air cooling used, are the open-vault concept and the closed-vault concept. The following aspects of these air-cooled vault storage facility concepts are discussed: description and operation of facilities; strucutral design considerations and analysis; nuclear design considerations and analyses; vault environmental design considerations; unique design features; and accident analysis

The December 7, 1988 Armenia earthquake effects on selected power, industrial and commercial facilities

International Nuclear Information System (INIS)

Campbell, R.D.; Griffin, M.J.; Bragagnolo, L.J.; Yanev, P.I.

1996-01-01

A detailed overview of the Armenia earthquake (occurred on December 7, 1988) effects on selected power, industrial and commercial facilities is presented in this paper. It involves geologic and seismology study of the region; description of the design building standards; detailed description of the damaged nuclear and other power plants as well as other industrial facilities. Extensive damage was sustained by the industrial facilities in the epicentral area, the majority due to poor design and construction. The effects on power facilities were much less severe. response time to restore power to the transmission was 2 to 3 days following the earthquake. Power plant equipment without rigorous seismic design performed well. Mechanical equipment, pumps, valves, compressors, and piping all performed with minimal damage, Electrical control equipment if properly anchored performed well without exception

Field Lysimeter Test Facility for protective barriers: Experimental plan

International Nuclear Information System (INIS)

Kirkham, R.R.; Gee, G.W.; Downs, J.L.

1987-12-01

This document was first written in October 1986 and has been used to guide the design of the Field Lysimeter Test Facility (FLTF) and to promote discussions between research and engineering staff regarding the selection of barrier treatments for inclusion in the FLTF. The construction of the lysimeter facility was completed June 28, 1987. This document describes the facility, the treatments placed in each lysimeter, types of measurements made in each lysimeter, and a brief discussion of project activities related to quality assurance, safety, and funding requirements. The treatment description and figures have been updated to reflect the lysimeter facility as constructed. 12 refs., 6 figs., 5 tabs

Baseline process description for simulating plutonium oxide production for precalc project

Energy Technology Data Exchange (ETDEWEB)

Pike, J. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-10-26

Savannah River National Laboratory (SRNL) started a multi-year project, the PreCalc Project, to develop a computational simulation of a plutonium oxide (PuO₂) production facility with the objective to study the fundamental relationships between morphological and physicochemical properties. This report provides a detailed baseline process description to be used by SRNL personnel and collaborators to facilitate the initial design and construction of the simulation. The PreCalc Project team selected the HB-Line Plutonium Finishing Facility as the basis for a nominal baseline process since the facility is operational and significant model validation data can be obtained. The process boundary as well as process and facility design details necessary for multi-scale, multi-physics models are provided.

Energy study of railroad freight transportation. Volume 2. Industry description

Energy Technology Data Exchange (ETDEWEB)

None

1979-08-01

The United States railroad industry plays a key role in transporting materials to support our industrial economy. One of the oldest industries in the US, the railroads have developed over 150 years into their present physical and operational configuration. Energy conservation proposals to change industry facilities, equipment, or operating practices must be evaluated in terms of their cost impact. A current, comprehensive and accurate data baseline of railroad economic activity and energy consumption is presented. Descriptions of the history of railroad construction in the US and current equipment, facilities, and operation practices follow. Economic models that relate cost and energy of railroad service to the volume of railroad output and to physical and operational parameters are provided. The analyses and descriptions should provide not only an analytical baseline for evaluating the impact of proposed conservation measures, but they should also provide a measure of understanding of the system and its operations to analysts and policy makers who are involved in proposing, analyzing, and implementing such changes.

Antecedents of Customer Relationship Termination

DEFF Research Database (Denmark)

Geersbro, Jens; Ritter, Thomas

To end business relationships, or to more actively terminate relationships, has long been acknowledged as part of customer relationship management. However, compared to other elements such as initiation and maintenance of relationships, little is known about the termination of business...... relationships as a managerial task. This paper contributes by (1) developing a conceptualization of relationship termination competence and (2) analyzing its antecedents. The empirical results identify termination acceptance, definition non-customers, organizational relationship termination routines......, and motivation as significant antecedents. Because of this, managers need to develop their organizations in order to use relationship termination as a vital strategy....

Preparations for decontamination and disposition of the Sodium Reactor Experiment (SRE) and other ERDA facilities at AI

International Nuclear Information System (INIS)

Heine, W.F.; Graves, A.W.

1975-01-01

The program plan for the decontamination and disposition of facilities at the Sodium Reactor Experiment and other ERDA-owned, AI-operated, radioactive facilities is described. The program objective along with a description of each of the subject facilities is presented. A description of the organizational structure within supporting the program is given. The elements of planning required to prepare for the task are detailed, including the requirements for cost and schedule control. Progress to date and the future plans are presented. The available technology utilized in the program is described

Behaviour Oriented of Leadership and the Utilization of Facilities Toward Students Satisfaction

OpenAIRE

Permono, Fannia Juwita; Suryana, Asep

2015-01-01

Vocational education is one of the institution to prepare the labors in industries. The aims of study are to describe and analyze behaviour oriented of leadership and the utilization of facilities toward students satisfaction. This study was done by descriptive analytic method. Data were collected by distributing questionnaire. Data were analyzed by using descriptive statistics. The study foundthat general description of the orientation of leadership behavoiur that is implemented by principal...

The EXCYT RIB facility at LNS

Energy Technology Data Exchange (ETDEWEB)

Ciavola, G. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Alba, R. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Calabretta, L. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Cuttone, G. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Di Bartolo, G. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Gammino, S. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Migneco, E. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Raia, G. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Rifuggiato, D. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Rovelli, A. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Sura, J. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Vinciguerra, D. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud; Wollnik, H. [Inst. Nazionale di Fisica Nucleare, Catania (Italy). Lab. Nazionale del Sud

1996-11-11

EXCYT, a project for a low energy ISOL facility at LNS, has been funded. It is based on two already existing particle accelerators. A K=800 superconducting cyclotron will deliver the primary beam of ions A{<=}48; E=50-80 MeV/amu. After its interaction in a thick target, the negatively ionized radioactive products (A<80) will be post-accelerated to 0.2-8 MeV/amu by a 15 MV SMP tandem. A description of the facility, including the fully redesigned ion optics, an overview of the design problems and the expected secondary beam intensities are presented. (orig.).

The EXCYT RIB facility at LNS

International Nuclear Information System (INIS)

Ciavola, G.; Alba, R.; Calabretta, L.; Cuttone, G.; Di Bartolo, G.; Gammino, S.; Migneco, E.; Raia, G.; Rifuggiato, D.; Rovelli, A.; Sura, J.; Vinciguerra, D.; Wollnik, H.

1996-01-01

EXCYT, a project for a low energy ISOL facility at LNS, has been funded. It is based on two already existing particle accelerators. A K=800 superconducting cyclotron will deliver the primary beam of ions A≤48; E=50-80 MeV/amu. After its interaction in a thick target, the negatively ionized radioactive products (A<80) will be post-accelerated to 0.2-8 MeV/amu by a 15 MV SMP tandem. A description of the facility, including the fully redesigned ion optics, an overview of the design problems and the expected secondary beam intensities are presented. (orig.)

Support facilities

International Nuclear Information System (INIS)

Williamson, F.S.; Blomquist, J.A.; Fox, C.A.

1977-01-01

Computer support is centered on the Remote Access Data Station (RADS), which is equipped with a 1000 lpm printer, 1000 cpm reader, and a 300 cps paper tape reader with 500-foot spools. The RADS is located in a data preparation room with four 029 key punches (two of which interpret), a storage vault for archival magnetic tapes, card files, and a 30 cps interactive terminal principally used for job inquiry and routing. An adjacent room provides work space for users, with a documentation library and a consultant's office, plus file storage for programs and their documentations. The facility has approximately 2,600 square feet of working laboratory space, and includes two fully equipped photographic darkrooms, sectioning and autoradiographic facilities, six microscope cubicles, and five transmission electron microscopes and one Cambridge scanning electron microscope equipped with an x-ray energy dispersive analytical system. Ancillary specimen preparative equipment includes vacuum evaporators, freeze-drying and freeze-etching equipment, ultramicrotomes, and assorted photographic and light microscopic equipment. The extensive physical plant of the animal facilities includes provisions for holding all species of laboratory animals under controlled conditions of temperature, humidity, and lighting. More than forty rooms are available for studies of the smaller species. These have a potential capacity of more than 75,000 mice, or smaller numbers of larger species and those requiring special housing arrangements. There are also six dog kennels to accommodate approximately 750 dogs housed in runs that consist of heated indoor compartments and outdoor exercise areas

MCO Monitoring activity description

International Nuclear Information System (INIS)

SEXTON, R.A.

1998-01-01

Spent Nuclear Fuel remaining from Hanford's N-Reactor operations in the 1970s has been stored under water in the K-Reactor Basins. This fuel will be repackaged, dried and stored in a new facility in the 200E Area. The safety basis for this process of retrieval, drying, and interim storage of the spent fuel has been established. The monitoring of MCOS in dry storage is a currently identified issue in the SNF Project. This plan outlines the key elements of the proposed monitoring activity. Other fuel stored in the K-Reactor Basins, including SPR fuel, will have other monitoring considerations and is not addressed by this activity description

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…

Conceptual modular description of the high-level waste management system for system studies model development

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1992-08-01

This document presents modular descriptions of possible alternative components of the federal high-level radioactive waste management system and the procedures for combining these modules to obtain descriptions for alternative configurations of that system. The 20 separate system component modules presented here can be combined to obtain a description of any of the 17 alternative system configurations (i.e., scenarios) that were evaluated in the MRS Systems Studies program (DOE 1989a). First-approximation descriptions of other yet-undefined system configurations could also be developed for system study purposes from this database. The descriptions include, in a modular format, both functional descriptions of the processes in the waste management system, plus physical descriptions of the equipment and facilities necessary for performance of those functions

Delivering information: A descriptive study of Australian women’s information needs for decision-making about birth facility

Directory of Open Access Journals (Sweden)

Thompson Rachel

2012-06-01

Full Text Available Abstract Background Little information is known about what information women want when choosing a birth facility. The objective of this study was to inform the development of a consumer decision support tool about birth facility by identifying the information needs of maternity care consumers in Queensland, Australia. Methods Participants were 146 women residing in both urban and rural areas of Queensland, Australia who were pregnant and/or had recently given birth. A cross-sectional survey was administered in which participants were asked to rate the importance of 42 information items to their decision-making about birth facility. Participants could also provide up to ten additional information items of interest in an open-ended question. Results On average, participants rated 30 of the 42 information items as important to decision-making about birth facility. While the majority of information items were valued by most participants, those related to policies about support people, other women’s recommendations about the facility, freedom to choose one’s preferred position during labour and birth, the aesthetic quality of the facility, and access to on-site neonatal intensive care were particularly widely valued. Additional items of interest frequently focused on postnatal care and support, policies related to medical intervention, and access to water immersion. Conclusions The women surveyed had significant and diverse information needs for decision-making about birth facility. These findings have immediate applications for the development of decision support tools about birth facility, and highlight the need for tools which provide a large volume of information in an accessible and user-friendly format. These findings may also be used to guide communication and information-sharing by care providers involved in counselling pregnant women and families about their options for birth facility or providing referrals to birth facilities.

Model Regulations for Decommissioning of Facilities

International Nuclear Information System (INIS)

2017-07-01

The IAEA has systematic programmes to provide Member States with the guidance, services and training necessary for establishing a legal and regulatory framework, including the planning and implementation of decommissioning. The model regulations provided in this publication cover all aspects of the planning, conduct and termination of the decommissioning of facilities and management of the associated waste, in accordance with the relevant requirements of the IAEA safety standards. They provide a framework for establishing regulatory requirements and conditions of authorization to be incorporated into individual authorizations for the decommissioning of specific facilities. The model regulations also establish criteria to be used for assessing compliance with regulatory requirements. The publication will be of assistance to Member States in appraising the adequacy of their existing regulations and regulatory guides, and serves as a reference for those Member States developing regulations for the first time.

Treatment compliance and challenges among tuberculosis patients across selected health facilities in Osun State Nigeria.

Science.gov (United States)

Ajao, K O; Ogundun, O A; Afolabi, O T; Ojo, T O; Atiba, B P; Oguntunase, D O

2014-12-01

Tuberculosis (TB) is a major public health problem in the world and Africa has approximately one quarter of the world's cases. One of the greatest challenges facing most TB programmes is the non-compliance to TB treatment among TB patients. This study aimed at determining the challenges of management of tuberculosis (TB) across selected Osun State health facilities. The study employed a descriptive cross-sectional design. A semi-structured questionnaire was used to collect data from 102 TB patients in the health facilities. The instrument measured socio-demographic variables, patient related factors, socio-economic variables, health care system related factors to TB disease and treatment. Data were analysed and summarized using descriptive and inferential statistics. Statistical significance was placed at p facilities (χ2 = 21.761, p facility and patient-related factors were largely responsible.

Visual operations management tools applied to the oil pipelines and terminals standardization process: the experience of TRANSPETRO

Energy Technology Data Exchange (ETDEWEB)

Almeida, Maria Fatima Ludovico de [Pontificia Universidade Catolica do Rio de Janeiro (PUC-Rio/ITUC), Rio de Janeiro, RJ (Brazil). Instituto Tecnologico; Santiago, Adilson; Ribeiro, Kassandra Senra; Arruda, Daniela Mendonca [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

2009-07-01

This paper describes the process by which visual operations management (VOM) tools were implemented, concerning standards and operational procedures in TRANSPETRO's Oil Pipelines and Terminals Unit. It provides: a brief literature review of visual operations management tools applied to total quality management and the standardization processes; a discussion of the assumptions from the second level of VOM (visual standards) upon which TRANSPETRO's oil pipelines and terminals business processes and operational procedures are based; and a description of the VOM implementation process involving more than 100 employees and one illustrative example of 'Quick Guides' for right-of- way management activities. Finally, it discusses the potential impacts and benefits of using VOM tools in the current practices in TRANSPETRO's Oil Pipelines and Terminals Unit, reinforcing the importance of such visual guides as vital to implement regional and corporate procedures, focusing on the main operational processes. (author)

Sub-scale Direct Connect Supersonic Combustion Facility (Research Cell 18)

Data.gov (United States)

Federal Laboratory Consortium — Description: RC18 is a continuous-flow, direct-connect, supersonic-combustion research facility that is capable of simulating flight conditions from Mach 3.0 to Mach...

Support for nurses directly involved with women who chose to terminate a pregnancy

Directory of Open Access Journals (Sweden)

AC Gmeiner

2000-09-01

Full Text Available Research conducted by Poggenpoel, Myburgh and Gmeiner (1998:2-8 on “One voice regarding the legalization of abortion: Nurses who experience discomfort” indicated that the nurses were in favour of the fact that nurses should volunteer to participate in terminating a pregnancy of a woman. From our observations in clinics where nurses voluntarily participate in providing reproductive health services, including termination of pregnancy, it became clear that supporting these nurses may be essential. To be able to provide support, it is necessary to identify, explore and describe nurses’ experience of being directly involved with women who terminate their pregnancy. To enable us to address the identified problems, a qualitative research strategy was implemented in which respondents were included in the sample through purposive sampling. Phenomenological interviews were conducted individually. Data was analysed by means of Tesch’s descriptive approach. Thereafter, guidelines for operationalisation were inferred from the results and a literature control completed to verify and enrich guidelines. Measures to ensure trustworthiness have been applied in the research and ethical measures have been strictly adhered to regarding this sensitive issue.

S.E.T., CSNI Separate Effects Test Facility Validation Matrix

International Nuclear Information System (INIS)

1997-01-01

1 - Description of test facility: The SET matrix of experiments is suitable for the developmental assessment of thermal-hydraulics transient system computer codes by selecting individual tests from selected facilities, relevant to each phenomena. Test facilities differ from one another in geometrical dimensions, geometrical configuration and operating capabilities or conditions. Correlation between SET facility and phenomena were calculated on the basis of suitability for model validation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant and is sufficiently instrumented); limited suitability for model variation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant but has problems associated with imperfect scaling, different test fluids or insufficient instrumentation); and unsuitability for model validation. 2 - Description of test: Whereas integral experiments are usually designed to follow the behaviour of a reactor system in various off-normal or accident transients, separate effects tests focus on the behaviour of a single component, or on the characteristics of one thermal-hydraulic phenomenon. The construction of a separate effects test matrix is an attempt to collect together the best sets of openly available test data for code validation, assessment and improvement, from the wide range of experiments that have been carried out world-wide in the field of thermal hydraulics. In all, 2094 tests are included in the SET matrix

40 CFR 63.11087 - What requirements must I meet for gasoline storage tanks if my facility is a bulk gasoline...

Science.gov (United States)

2010-07-01

... gasoline storage tanks if my facility is a bulk gasoline terminal, pipeline breakout station, or pipeline... CATEGORIES (CONTINUED) National Emission Standards for Hazardous Air Pollutants for Source Category: Gasoline... § 63.11087 What requirements must I meet for gasoline storage tanks if my facility is a bulk gasoline...

Physics Division Argonne National Laboratory description of the programs and facilities.

Energy Technology Data Exchange (ETDEWEB)

Thayer, K.J. [ed.

1999-05-24

The ANL Physics Division traces its roots to nuclear physics research at the University of Chicago around the time of the second world war. Following the move from the University of Chicago out to the present Argonne site and the formation of Argonne National Laboratory: the Physics Division has had a tradition of research into fundamental aspects of nuclear and atomic physics. Initially, the emphasis was on areas such as neutron physics, mass spectrometry, and theoretical studies of the nuclear shell model. Maria Goeppert Maier was an employee in the Physics Division during the time she did her Nobel-Prize-winning work on the nuclear shell model. These interests diversified and at the present time the research addresses a wide range of current problems in nuclear and atomic physics. The major emphasis of the current experimental nuclear physics research is in heavy-ion physics, centered around the ATLAS facility (Argonne Tandem-Linac Accelerator System) with its new injector providing intense, energetic ion beams over the fill mass range up to uranium. ATLAS is a designated National User Facility and is based on superconducting radio-frequency technology developed in the Physics Division. A small program continues in accelerator development. In addition, the Division has a strong program in medium-energy nuclear physics carried out at a variety of major national and international facilities. The nuclear theory research in the Division spans a wide range of interests including nuclear dynamics with subnucleonic degrees of freedom, dynamics of many-nucleon systems, nuclear structure, and heavy-ion interactions. This research makes contact with experimental research programs in intermediate-energy and heavy-ion physics, both within the Division and on the national and international scale. The Physics Division traditionally has strong connections with the nation's universities. We have many visiting faculty members and we encourage students to participate in our

The Relationship between Facility-Based Delivery and Infant Immunization in sub-Saharan Africa.

Science.gov (United States)

Moyer, Cheryl A; Benyas, Dana; Rominski, Sarah

2016-06-01

This study explored the relationship between facility-based delivery and infant immunizations in sub-Saharan Africa, controlling for economic development indicators. Publically available data were collected and imported into Stata 11.0 for descriptive, correlation, and regression analyses. Facility delivery was significantly associated with full vaccination and BCG immunization in children aged 12-23 months. Facility delivery was associated with full vaccination (phealthcare system.

Technical description - interim storage, encapsulation and disposal of spent nuclear fuel

International Nuclear Information System (INIS)

2010-07-01

The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test

LNG TERMINAL SAFE OPERATION MANAGEMENT

Directory of Open Access Journals (Sweden)

Andrzej ADAMKIEWICZ

2012-07-01

Full Text Available This article presents the significance of LNG terminal safety issues in natural gas sea transport. It shows particular requirements for LNG transmission installations resulting from the specific properties of LNG. Out of the multi‐layer critical safety areas comprising structural elements of the terminal safety system, possibilities to decrease the risk of emergency occurrence on LNG terminals have been selected. Tasks performed by the LNG terminal, together with its own personnel and the outside one, have been defined. General theses for LNG terminal safety have been formulated.

Grout Facilities standby plan

Energy Technology Data Exchange (ETDEWEB)

Claghorn, R.D.; Kison, P.F.; Nunamaker, D.R.; Yoakum, A.K.

1994-09-29

This plan defines how the Grout Facilities will be deactivated to meet the intent of the recently renegotiated Tri-Party Agreement (TPA). The TPA calls for the use of the grout process as an emergency option only in the event that tank space is not available to resolve tank safety issues. The availability of new tanks is expected by 1997. Since a grout startup effort would take an estimated two years, a complete termination of the Grout Disposal Program is expected in December 1995. The former Tank Waste Remediation (TWRS) Strategy, adopted in 1988, called for the contents of Hanford`s 28 newer double-shell waste tanks to be separated into high-level radioactive material to be vitrified and disposed of in a geologic repository; low-level wastes were to be sent to the Grout Facility to be made into a cement-like-mixture and poured into underground vaults at Hanford for disposal. The waste in the 149 older single-shell tanks (SST) were to undergo further study and analysis before a disposal decision was made.

Grout Facilities standby plan

International Nuclear Information System (INIS)

Claghorn, R.D.; Kison, P.F.; Nunamaker, D.R.; Yoakum, A.K.

1994-01-01

This plan defines how the Grout Facilities will be deactivated to meet the intent of the recently renegotiated Tri-Party Agreement (TPA). The TPA calls for the use of the grout process as an emergency option only in the event that tank space is not available to resolve tank safety issues. The availability of new tanks is expected by 1997. Since a grout startup effort would take an estimated two years, a complete termination of the Grout Disposal Program is expected in December 1995. The former Tank Waste Remediation (TWRS) Strategy, adopted in 1988, called for the contents of Hanford's 28 newer double-shell waste tanks to be separated into high-level radioactive material to be vitrified and disposed of in a geologic repository; low-level wastes were to be sent to the Grout Facility to be made into a cement-like-mixture and poured into underground vaults at Hanford for disposal. The waste in the 149 older single-shell tanks (SST) were to undergo further study and analysis before a disposal decision was made

Geothermal energy conversion facility

Energy Technology Data Exchange (ETDEWEB)

Kutscher, C.F.

1997-12-31

With the termination of favorable electricity generation pricing policies, the geothermal industry is exploring ways to improve the efficiency of existing plants and make them more cost-competitive with natural gas. The Geothermal Energy Conversion Facility (GECF) at NREL will allow researchers to study various means for increasing the thermodynamic efficiency of binary cycle geothermal plants. This work has received considerable support from the US geothermal industry and will be done in collaboration with industry members and utilities. The GECF is being constructed on NREL property at the top of South Table Mountain in Golden, Colorado. As shown in Figure 1, it consists of an electrically heated hot water loop that provides heating to a heater/vaporizer in which the working fluid vaporizes at supercritical or subcritical pressures as high as 700 psia. Both an air-cooled and water-cooled condenser will be available for condensing the working fluid. In order to minimize construction costs, available equipment from the similar INEL Heat Cycle Research Facility is being utilized.

The experimental facility of Tournemire; La station experimentale de Tournemire

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-10-01

This document presents the underground facility of Tournemire (Aveyron, France). The Tournemire abandoned railway tunnel gives access to a 250 m thick Jurassic clay bed covered with 250 m of limestones. The main goal of the Tournemire project is the study of the mechanical properties and fracturing of a clay formation and of its ability to be used as a deep underground storage facility for radioactive wastes. The document comprises a general presentation brochure and a description of the geologic, tectonic, geomechanical and hydro-geochemical surveys carried out in the facility. (J.S.)

A new 14C AMS facility at IUAC, New Delhi

International Nuclear Information System (INIS)

Kumar, Pankaj; Ojha, S.; Sharma, R.; Gargari, S.; Joshi, R.; Chopra, S.; Kanjilal, D.

2015-01-01

A new state of art Accelerator Mass Spectrometry (AMS) facility for 14 C has been developed at IUAC. This facility is based on the 0.5 MV Pelletron accelerator and an Automated Graphitization Equipment (AGE). In addition to the 14 C measurements, this system has the capability to perform 10 Be and 26 AI measurements also. The system is called XCAMS i.e., Compact, Accelerator Mass Spectrometer eXtended for 10 Be and 26 AI. A detailed description of the newly developed AMS facility and the recent measurements will be discussed

Nonleaking battery terminals.

Science.gov (United States)

Snider, W. E.; Nagle, W. J.

1972-01-01

Three different terminals were designed for usage in a 40 ampere/hour silver zinc battery which has a 45% KOH by weight electrolyte in a plastic battery case. Life tests, including thermal cycling, electrical charge and discharge for up to three years duration, were conducted on these three different terminal designs. Tests for creep rate and tensile strength were conducted on the polyphenylene oxide plastic battery cases. Some cases were unused and others containing KOH electrolyte were placed on life tests. The design and testing of nonleaking battery terminals for use with a KOH electrolyte in a plastic case are considered.

OPG Western Waste Management Facility

Energy Technology Data Exchange (ETDEWEB)

Julian, J. [Ontario Power Generation, Western Waste Management Facility, Tiverton, ON (Canada)

2011-07-01

The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)

OPG Western Waste Management Facility

International Nuclear Information System (INIS)

Julian, J.

2011-01-01

The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)

Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

International Nuclear Information System (INIS)

1986-09-01

This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

Cold Vacuum Drying facility condensate collection system design description (SYS 19); FINAL

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) condensate collection system (CCS). The function of the CCS is to collect cooling coil condensate from air-handling units in the CVDF and to isolate the condensate in collection tanks until the condensate is determined to be acceptable to drain to the effluent drain collection basin

High Temperature Test Facility Preliminary RELAP5-3D Input Model Description

Energy Technology Data Exchange (ETDEWEB)

Bayless, Paul David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-12-01

A RELAP5-3D input model is being developed for the High Temperature Test Facility at Oregon State University. The current model is described in detail. Further refinements will be made to the model as final as-built drawings are released and when system characterization data are available for benchmarking the input model.

A high pressure sample facility for neutron scattering

International Nuclear Information System (INIS)

Carlile, C.J.; Glossop, B.H.

1981-06-01

Commissioning tests involving deformation studies and tests to destruction as well as neutron diffraction measurements of a standard sample have been carried out on the SERC high pressure sample facility for neutron scattering studies. A detailed description of the pressurising equipment is given. (author)

Description of the RA-3 research reactor as a model facility

International Nuclear Information System (INIS)

Vicens, Hugo E.; Quintana, Jorge A.

2001-01-01

The Argentine RA-3 reactor is described as a model facility for the information to be provided to the IAEA in accordance with the requirements of the Model Additional Protocol. RA-3 reactor was designed as a 5 MW swimming pool reactor, moderated and cooled with light water. Its fuel was 90% enriched uranium. The reactor started its operation in 1967, has been modified and improved in many components, including the core, that now is fueled with moderately enriched uranium

Installation of Cacouna Energy's liquefied natural gas terminal : public inquiry report; Projet d'implantation du terminal methanier Energie Cacouna : rapport d'enquete et d'audience publique

Energy Technology Data Exchange (ETDEWEB)

Cosgrove, W.J. (comp.)

2006-11-15

This paper discussed the proposed construction of a liquefied natural gas (LNG) terminal 15 km northeast of Riviere-du-Loup, Quebec, in area that has strong land and marine biodiversity. The proposed project to import LNG for the North American market would involve the construction of ship docking facilities, transhipment facilities, and ground storage facilities. Quebec's environmental agency, the Bureau d'audiences publiques sur l'environnement (BAPE) examined the sustainability of the project with respect to biophysical aspects, social, economic and cultural development, as well as the environment, health, and public safety. Public hearings for the project attracted many citizens, First Nation groups and corporations with two opinions, for and against the project. Those in favour mentioned that Quebec must diversify its usual source of LNG from the west and that the project would promote competition. People at the public hearing expressed concerns for the quality of life, public health, air quality, noise pollution, visual impairment of the landscape, the security related to the operations of the terminal and navigation, public safety, recreational activities, marine mammals, fish, birds, animals, marshlands, greenhouse gas emissions, water pollution and soil pollution. This paper also outlined the state of the North-American market for LNG and its evolution; LNG supply and demand for the next twenty years; changes in gas prices; and emergency planning for the implementation of the project. BAPE recommended that the environmental monitoring and tracking be done by a project proponent. It was concluded that the proposed project would create competition with western Canada due to continually higher LNG prices, and would promote local jobs during the construction phase. 41 refs., 7 tabs., 8 figs.

Automating an EXAFS facility: hardware and software considerations

International Nuclear Information System (INIS)

Georgopoulos, P.; Sayers, D.E.; Bunker, B.; Elam, T.; Grote, W.A.

1981-01-01

The basic design considerations for computer hardware and software, applicable not only to laboratory EXAFS facilities, but also to synchrotron installations, are reviewed. Uniformity and standardization of both hardware configurations and program packages for data collection and analysis are heavily emphasized. Specific recommendations are made with respect to choice of computers, peripherals, and interfaces, and guidelines for the development of software packages are set forth. A description of two working computer-interfaced EXAFS facilities is presented which can serve as prototypes for future developments. 3 figures

Determination of the state of operating mechanical stresses acting on surface piping with problems of differential collapses in the Venta de Carpio Terminal; Determinacion del estado de esfuerzos mecanicos actuantes en tuberias superficiales con problemas de hundimientos diferenciales en la Terminal Venta de Carpio

Energy Technology Data Exchange (ETDEWEB)

Neri B, Ernesto R; Garcia E, Nairoby [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

2004-07-01

The Venta de Carpio Terminal is located in the Northern part of the old Texcoco Lake, State of Mexico, in highly compressible soil. In it, it is received, regulated, measured and distributed natural gas, LP gas and PEMEX Refinacion products that are supplied to distribution terminals of and consumption centers located in the central area of the country, that encompasses the states of Puebla, Tlaxcala, Mexico, Hidalgo, Queretaro and a small part of the Federal District. The construction of the Venta de Carpio station dates from 1960; since then, it has presented important regional settlements, mainly due to the water extraction of the subsoil, that have imposed deformations to the piping systems connected to the surface facilities that have been piloted in the terminal. Equally, other surface piping systems and facilities present deformations by differential settlement between their supports. [Spanish] La Terminal Venta de Carpio se ubica en la parte norte del antiguo Lago de Texcoco, Estado de Mexico, en terreno altamente compresible. En ella, se recibe, regula, mide y distribuye gas natural, gas LP y productos de Pemex Refinacion que se suministran a terminales de distribucion y centros de consumo localizados en el area central del pais, que comprende los estados de Puebla, Tlaxcala, Mexico, Hidalgo, Queretaro y una pequena parte del Distrito Federal. La construccion de la estacion Venta de Carpio data de 1960; desde entonces, se han presentado asentamientos regionales importantes debidos, principalmente a la extraccion de agua del subsuelo, que han impuesto deformaciones a los sistemas de tuberias conectados con las instalaciones superficiales que han sido piloteadas en la terminal. De igual modo, otros sistemas de tuberias e instalaciones superficiales presentan deformaciones por hundimientos diferenciales entre sus apoyos.

Idaho National Engineering Laboratory irradiation facilities and their applications

International Nuclear Information System (INIS)

Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

1986-05-01

Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

International Nuclear Information System (INIS)

1985-09-01

In April 1985, the Department of Energy (DOE) selected the Clinch River site as its preferred site for the construction and operation of the monitored retrievable storage (MRS) facility (USDOE, 1985). In support of the DOE MRS conceptual design activity, available data describing the site have been gathered and analyzed. A composite geotechnical description of the Clinch River site has been developed and is presented herein. This report presents Clinch River site description data in the following sections: general site description, surface hydrologic characteristics, groundwater characteristics, geologic characteristics, vibratory ground motion, surface faulting, stability of subsurface materials, slope stability, and references. 48 refs., 35 figs., 6 tabs

Intrinsic terminators in Mycoplasma hyopneumoniae transcription.

Science.gov (United States)

Fritsch, Tiago Ebert; Siqueira, Franciele Maboni; Schrank, Irene Silveira

2015-04-08

Mycoplasma hyopneumoniae, an important pathogen of swine, exhibits a low guanine and cytosine (GC) content genome. M. hyopneumoniae genome is organised in long transcriptional units and promoter sequences have been mapped upstream of all transcription units. These analysis provided insights into the gene organisation and transcription initiation at the genome scale. However, the presence of transcriptional terminator sequences in the M. hyopneumoniae genome is poorly understood. In silico analyses demonstrated the presence of putative terminators in 82% of the 33 monocistronic units (mCs) and in 74% of the 116 polycistronic units (pCs) considering different classes of terminators. The functional activity of 23 intrinsic terminators was confirmed by RT-PCR and qPCR. Analysis of all terminators found by three software algorithms, combined with experimental results, allowed us to propose a pattern of RNA hairpin formation during the termination process and to predict the location of terminators in the M. hyopneumoniae genome sequence. The stem-loop structures of intrinsic terminators of mycoplasma diverge from the pattern of terminators found in other bacteria due the low content of guanine and cytosine. In M. hyopneumoniae, transcription can end after a transcriptional unit and before its terminator sequence and can also continue past the terminator sequence with RNA polymerases gradually releasing the RNA.

Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

International Nuclear Information System (INIS)

Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

2011-01-01

In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

Visual operations management tools applied to the oil pipelines and terminals standardization process: the experience of TRANSPETRO

Energy Technology Data Exchange (ETDEWEB)

Almeida, Maria Fatima Ludovico de [Pontificia Universidade Catolica do Rio de Janeiro (PUC-Rio/ITUC), Rio de Janeiro, RJ (Brazil). Instituto Tecnologico; Santiago, Adilson; Ribeiro, Kassandra Senra; Arruda, Daniela Mendonca [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

2009-07-01

This paper describes the process by which visual operations management (VOM) tools were implemented, concerning standards and operational procedures in TRANSPETRO's Oil Pipelines and Terminals Unit. It provides: a brief literature review of visual operations management tools applied to total quality management and the standardization processes; a discussion of the assumptions from the second level of VOM (visual standards) upon which TRANSPETRO's oil pipelines and terminals business processes and operational procedures are based; and a description of the VOM implementation process involving more than 100 employees and one illustrative example of 'Quick Guides' for right-of- way management activities. Finally, it discusses the potential impacts and benefits of using VOM tools in the current practices in TRANSPETRO's Oil Pipelines and Terminals Unit, reinforcing the importance of such visual guides as vital to implement regional and corporate procedures, focusing on the main operational processes. (author)

Status of spent fuel storage facilities in Switzerland

International Nuclear Information System (INIS)

Beyeler, P.C.; Lutz, H.R.; Heesen, W. von

1999-01-01

Planning of a dry spent fuel storage facility in Switzerland started already 15 years ago. The first site considered for a central interim storage facility was the cavern of the decommissioned pilot nuclear plant at Lucens in the French-speaking part of Switzerland. This project was terminated in the late eighties because of lack of public acceptance. The necessary acceptance was found in the small town of Wuerenlingen which has hosted for many years the Swiss Reactor Research Centre. The new project consists of centralised interim storage facilities for all types of radioactive waste plus a hot cell and a conditioning and incinerating facility. It represents a so-called integrated storage solution. In 1990, the new company 'ZWILAG Zwischenlager Wuerenlingen AG' (ZWILAG) was founded and the licensing procedures according to the Swiss Atomic law were initiated. On August 26, 1996 ZWILAG got the permit for construction of the whole facility including the operating permit for the storage facilities. End of construction and commissioning are scheduled for autumn 1999. The nuclear power station Beznau started planning a low level waste and spent fuel storage facility on its own, because in 1990 its management thought that by 1997 the first high active waste from the reprocessing facilities in France would have to be taken back. This facility at the Beznau site, called ZWIBEZ, was licensed according to a shorter procedure so its construction was finished by 1997. The two facilities for high level waste and spent fuel provide space for a total of 278 casks, which is sufficient for the waste and spent fuel of the four Swiss nuclear power stations including their life extension programme. (author)

40 CFR 63.11088 - What requirements must I meet for gasoline loading racks if my facility is a bulk gasoline...

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 14 2010-07-01 2010-07-01 false What requirements must I meet for gasoline loading racks if my facility is a bulk gasoline terminal, pipeline breakout station, or pipeline... § 63.11088 What requirements must I meet for gasoline loading racks if my facility is a bulk gasoline...

40 CFR 63.11089 - What requirements must I meet for equipment leak inspections if my facility is a bulk gasoline...

Science.gov (United States)

2010-07-01

... equipment leak inspections if my facility is a bulk gasoline terminal, bulk plant, pipeline breakout station... gasoline service at the facility. (c) Each detection of a liquid or vapor leak shall be recorded in the log... shall be completed within 15 calendar days after detection of each leak, except as provided in paragraph...

Current personnel dosimetry practices at DOE facilities

International Nuclear Information System (INIS)

Fix, J.J.

1981-05-01

Only three parameters were included in the personnel occupational exposure records by all facilities. These are employee name, social security number, and whole body dose. Approximate percentages of some other parameters included in the record systems are sex (50%), birthdate (90%), occupation (26%), previous employer radiation exposure (74%), etc. Statistical analysis of the data for such parameters as sex versus dose distribution, age versus dose distribution, cumulative lifetime dose, etc. was apparently seldom done. Less than 50% of the facilities reported having formal documentation for either the dosimeter, records system, or reader. Slightly greater than 50% of facilities reported having routine procedures in place. These are considered maximum percentages because some respondents considered computer codes as formal documentation. The repository receives data from DOE facilities regarding the (a) distribution of annual whole body doses, (b) significant internal depositions, and (c) individual doses upon termination. It is expected that numerous differences exist in the dose data submitted by the different facilities. Areas of significant differences would likely include the determination of non-measurable doses, the methods used to determine previous employer radiation dose, the methods of determining cumulative radiation dose, and assessment of internal doses. Undoubtedly, the accuracy of the different dosimetry systems, especially at low doses, is very important to the credibility of data summaries (e.g., man-rem) provided by the repository

LNG TERMINAL SAFE OPERATION MANAGEMENT

OpenAIRE

Andrzej ADAMKIEWICZ; Włodzimierz KAMIŃSKI

2012-01-01

This article presents the significance of LNG terminal safety issues in natural gas sea transport. It shows particular requirements for LNG transmission installations resulting from the specific properties of LNG. Out of the multi‐layer critical safety areas comprising structural elements of the terminal safety system, possibilities to decrease the risk of emergency occurrence on LNG terminals have been selected. Tasks performed by the LNG terminal, together with its own personnel and the out...

Analysis on working pressure selection of ACME integral test facility

International Nuclear Information System (INIS)

Chen Lian; Chang Huajian; Li Yuquan; Ye Zishen; Qin Benke

2011-01-01

An integral effects test facility, advanced core cooling mechanism experiment facility (ACME) was designed to verify the performance of the passive safety system and validate its safety analysis codes of a pressurized water reactor power plant. Three test facilities for AP1000 design were introduced and review was given. The problems resulted from the different working pressures of its test facilities were analyzed. Then a detailed description was presented on the working pressure selection of ACME facility as well as its characteristics. And the approach of establishing desired testing initial condition was discussed. The selected 9.3 MPa working pressure covered almost all important passive safety system enables the ACME to simulate the LOCAs with the same pressure and property similitude as the prototype. It's expected that the ACME design would be an advanced core cooling integral test facility design. (authors)

Project description: ORNL PWR blowdown heat transfer separate-effects program, Thermal-Hydraulic Test Facility (THTF)

International Nuclear Information System (INIS)

1976-02-01

The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal-Hydraulic Test Facility (THTF), a large nonnuclear pressurized-water loop that incorporates a 49-rod electrically heated bundle. Supporting experiments will be carried out in two additional test loops - the Forced Convection Test Facility (FCTF), a small high-pressure facility in which single heater rods can be tested in annular geometry; and an air-water loop which is used to evaluate two-phase flow-measuring instrumentation

Design concept of radiation control system for the high intensity proton accelerator facility

Energy Technology Data Exchange (ETDEWEB)

Miyamoto, Yukihiro; Ikeno, Koichi; Akiyama, Shigenori; Harada, Yasunori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-11-01

Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics. (author)

The measurement of vacuum at high voltage terminal of the FOTIA facility at BARC

International Nuclear Information System (INIS)

Kansara, M.J.; Sapna, P.; Subrahmanyam, N.B.V.; Bhatt, J.P.; Gupta, S.K.; Singh, P.

2003-01-01

Full text: In FOTIA, the ion beams accelerated by the low energy tube are injected into the high-energy accelerating tube using the 180 deg folding magnet. In order to have maximum transmission through the magnet chamber the vacuum in this section should be in the range of 10 -8 Torr. The chamber is very narrow (14 mm x 24 mm) and offers low conductance to the vacuum system. For maintaining the required UHV inside this chamber and associated beam lines inside the high voltage terminal at 6 MV, a sputter ion pump (120 litres/sec) is used. However, the control of the ion pump and measurement of the vacuum in the chamber has to be done from the control consol located at ground potential. This has been accomplished through a fibre optic data telemetry system, which offers electrical isolation of 6 MV. This fibre optic system is integrated to the main control system of the FOTIA. For controlling and monitoring the ion pump DOUT and ADC modules of the CAMAC system are used to provide interfacing signals to the fibre optic system. For the measurement of the vacuum, the gauge output provided by the ion pump is converted to a suitable light signal (1 kHz to 10 kHz) and is transmitted to the fibre optic link box (located at ground). At ground level this light signal is converted back to a voltage signal and transmitted to ADC module of the CAMAC system. This voltage signal is calibrated against the vacuum measured in the terminal, which is available in the control room via computer connected to the CAMAC system. In this paper, details of the above system will be presented

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 7

International Nuclear Information System (INIS)

Owen, P.T.; Michelson, D.C.; Knox, N.P.; Fowler, J.W.

1986-09-01

The 644 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the seventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. References are arranged alphabetically by leading author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations

Termination unit

Energy Technology Data Exchange (ETDEWEB)

Traeholt, Chresten; Willen, Dag; Roden, Mark; Tolbert, Jerry C.; Lindsay, David; Fisher, Paul W.; Nielsen, Carsten Thidemann

2016-05-03

Cable end section comprises end-parts of N electrical phases/neutral, and a thermally-insulation envelope comprising cooling fluid. The end-parts each comprises a conductor and are arranged with phase 1 innermost, N outermost surrounded by the neutral, electrical insulation being between phases and N and neutral. The end-parts comprise contacting surfaces located sequentially along the longitudinal extension of the end-section. A termination unit has an insulating envelope connected to a cryostat, special parts at both ends comprising an adapter piece at the cable interface and a closing end-piece terminating the envelope in the end-section. The special parts houses an inlet and/or outlet for cooling fluid. The space between an inner wall of the envelope and a central opening of the cable is filled with cooling fluid. The special part at the end connecting to the cryostat houses an inlet or outlet, splitting cooling flow into cable annular flow and termination annular flow.

Minor Actinide Laboratory at JRC-ITU: Fuel fabrication facility

International Nuclear Information System (INIS)

Fernandez, A.; McGinley, J.; Somers, J.

2008-01-01

The Minor Actinide Laboratory (MA-lab) of the Institute for Transuranium Elements is a unique facility for the fabrication of fuels and targets containing minor actinides (MA). It is of key importance for research on Partitioning and Transmutation in Europe, as it is one of the only dedicated facilities for the fabrication of MA containing materials, either for property measurements or for the production of test pins for irradiation experiments. In this paper a detailed description of the MA-Lab facility and the fabrication processes developed to fabricate fuels and samples containing high content of minor actinides is given. In addition, experience gained and improvements are also outlined. (authors)

Spent nuclear fuel project cold vacuum drying facility operations manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

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

ORNL shielded facilities capable of remote handling of highly radioactive beta--gamma emitting materials

International Nuclear Information System (INIS)

Whitson, W.R.

1977-09-01

A survey of ORNL facilities having adequate shielding and containment for the remote handling of experimental quantities of highly radioactive beta-gamma emitting materials is summarized. Portions of the detailed descriptions of these facilities previously published in ORNL/TM-1268 are still valid and are repeated

Experimental facilities for calibrations at the dosimetry facility of group 6.5 'Neutron dosimetry' at the Physikalisch-Technische Bundesanstalt

International Nuclear Information System (INIS)

Strzelczyk, H.

1986-07-01

The mechanical and electrical layout of the ''Dosimetriemessplatz'', a low scattering target area at the accelerator facility is described. Monoenergetic neutrons are generated at the irradiation facility for the research on neutron detectors and dosimeters for radiation protection. The report is aimed to inform dosimetry in particular for those guest's coming from other laboratories. For that purpose a detailed description is given of the mechanical construction, of cable connections and of the monitor system. The feasibitity of data transfer from the system at the target position to the user's system and the mode of acceptance of external data are explained. (orig./HP) [de

Resource Conservation and Recovery Act Closure Plan for the Y-12 9409-5 Tank Storage Facility

International Nuclear Information System (INIS)

1995-02-01

This document presents information on the closure of the Y-12 9409-5 Tank Storage Facility. Topics discussed include: facility description; closure history; closure performance standard; partial closure; maximum waste inventory; closure activities; schedule; and postclosure care

The gravitational plant physiology facility-Description of equipment developed for biological research in spacelab

Science.gov (United States)

Heathcote, D. G.; Chapman, D. K.; Brown, A. H.; Lewis, R. F.

1994-01-01

In January 1992, the NASA Suttle mission STS 42 carried a facility designed to perform experiments on plant gravi- and photo-tropic responses. This equipment, the Gravitational Plant Physiology Facility (GPPF) was made up of a number of interconnected units mounted within a Spacelab double rack. The details of these units and the plant growth containers designed for use in GPPF are described. The equipment functioned well during the mission and returned a substantial body of time-lapse video data on plant responses to tropistic stimuli under conditions of orbital microgravity. GPPF is maintained by NASA Ames Research Center, and is flight qualifiable for future spacelab missions.

Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

National waste terminal storage program. Supplementary quality-assurance requirements

International Nuclear Information System (INIS)

Garland, D.L.

1980-01-01

The basic Quality Assurance Program Requirements standard for the National Waste Terminal Storage Program has been developed primarily for nuclear reactors and other fairly well established nuclear facilities. In the case of waste isolation, however, there are many ongoing investigations for which quality assurance practices and requirements have not been well defined. This paper points out these problems which require supplementary requirements. Briefly these are: (1) the language barrier, that is geologists and scientists are not familiar with quality assurance (QA) terminology; (2) earth sciences deal with materials that cannot be characterized as easily as metals or other materials that are reasonably homogeneous; (3) development and control of mathematical models and associated computer programs; (4) research and development

LASL experimental engineered waste burial facility: design considerations and preliminary plan

International Nuclear Information System (INIS)

DePoorter, G.L.

1980-01-01

The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

A description of the BNL active surface analysis facility

International Nuclear Information System (INIS)

Tyler, J.W.

1989-11-01

Berkeley Nuclear Laboratories has a responsibility for the assessment of radioactive specimens arising both from post irradiation examination of power reactor components and structures and experimental programmes concerned with fission and activation product transport. Existing analytical facilities have been extended with the commissioning of an active surface analysis instrument (XSAM 800pci, Kratos Analytical). Surface analysis involves the characterisation of the outer few atomic layers of a solid surface/interface whose chemical composition and electronic structure will probably be different from the bulk. The new instrument consists three interconnected chambers positioned in series; comprising of a high vacuum sample introduction chamber, an ultra-high vacuum sample treatment/fracture chamber and an ultra-high vacuum sample analysis chamber. The sample analysis chamber contains the electron, X-ray and ion-guns and the electron and ion detectors necessary for performing X-ray photoelectron spectroscopy, scanning Auger microscopy and secondary-ion mass spectroscopy. The chamber also contains a high stability manipulator to enable sub-micron imaging of specimens to be achieved and provide sample heating and cooling between - 180 and 600 0 C. (author)

Descriptive analysis of measles cases seen in a tertiary health facility in Sokoto, Northwest Nigeria – implication of disease eradication

Directory of Open Access Journals (Sweden)

Mohammed Yahaya

2017-01-01

Full Text Available Introduction Measles is a vaccine preventable viral disease that affects mostly children under-five years of age. It is highly contagious infection associated with high morbidity and mortality. Objective To describe the morbidity and mortality pattern of measles cases in person, place and time. Methods A health facility based study and cross sectional descriptive study design was used. All cases of measles that presented at the facility from January to June 2016 were profiled and their medical records reviewed. Representative blood samples were taken and analyzed using the Enzyme linked immunosorbent assay (ELISA method for the diagnosis of measles. Data was entered into MS Excel version 2016 and later analysed using Epi-info version 7. Results A total of 149 patients were seen over a period of 6 months. They represent 88 males and 61 females with a male to female ratio of 2:1. The median age of the cases was 30 months (range of 108 months to 9 month. The trend analysis shows a steady increased in number of cases from January with the month of March having the highest number of 46 cases, then there was steady decline for the subsequent months. Only 14 children, which accounted for 9.4% were reported to have being vaccinated against measles, while majority, 135 that represented 90.6% were not. Seven deaths were recorded; all were males and among cases that never received vaccine against measles, giving Case fatality rate (CFR of 5.0%. Measles specific immunoglobulin M (IgM was detected in all the blood samples that were sent for investigations. Conclusion Nearly all the cases did not receive measles vaccine and among the deaths recorded, none had been vaccinated against measles. Concerted efforts are required by all stakeholders to ensure every child is completely immunized in line with the global measles elimination strategy.

Radiochemical Facility Laboratory (RFL). Description of the installation and reprogramming of its objectives

International Nuclear Information System (INIS)

Bonini, Alberto; Dominguez, C.; Dell'Occhio, Leonor A.; Stankevicius, Alejandro

1999-01-01

A description is made of a laboratory that will be used to characterize radioactive wastes, to study the burnup of fuel elements, to make isotopic analysis by mass spectroscopy and to recover fissile materials from the production of fission 99 Mo. The equipment and the ventilation system are also described. (author)

Replacement Power Facility site selection report

Energy Technology Data Exchange (ETDEWEB)

Wike, L.D.; Toole, G.L.; Specht, W.L.

1992-06-01

The Department of Energy (DOE) has proposed the construction and operation of a Replacement Power Facility (RPF) for supplementing and replacing existing sources of steam and possibly electricity at the Savannah River Site (SRS). DOE is preparing an Environmental Impact Statement (EIS) for this project As part of the impact analysis of the proposed action, the EIS will include a detailed description of the environment where the RPF will be constructed. This description must be specific to the recommended site at SRS, which contains more than 300 square miles of land including streams, lakes, impoundments, wetlands, and upland areas. A formal site-selection process was designed and implemented to identify the preferred RPF site.

Quadrant I description of current conditions

International Nuclear Information System (INIS)

1990-09-01

In accordance with the requirements of the Consent Decree issued by the Ohio Attorney General's office on August 29, 1989 and with the RCRA Section 3008(h) Consent Order issued by the US Environmental Protection Agency, Region V (USEPA) on September 29, 1989, this report, which provides a Description of Current Conditions within Quadrant I of the Portsmouth Gaseous Diffusion Plant (PORTS) located in Piketon, Ohio, has been developed and submitted for approval. The objectives of this report are to provide data concerning: (1) the current state of knowledge of the environmental setting of Quadrant I of PORTS including ground water, surface water, soil and air; and (2) the extent of known, potential and suspected contamination of these segments of the environment in Quadrant I of the facility. This report is the initial step in the comprehensive RCRA Facility Investigation (RFI) currently underway at PORTS, and will provide a foundation for all subsequent activities related to the RFI in Quadrant I

HCIDL: Human-computer interface description language for multi-target, multimodal, plastic user interfaces

Directory of Open Access Journals (Sweden)

Lamia Gaouar

2018-06-01

Full Text Available From the human-computer interface perspectives, the challenges to be faced are related to the consideration of new, multiple interactions, and the diversity of devices. The large panel of interactions (touching, shaking, voice dictation, positioning … and the diversification of interaction devices can be seen as a factor of flexibility albeit introducing incidental complexity. Our work is part of the field of user interface description languages. After an analysis of the scientific context of our work, this paper introduces HCIDL, a modelling language staged in a model-driven engineering approach. Among the properties related to human-computer interface, our proposition is intended for modelling multi-target, multimodal, plastic interaction interfaces using user interface description languages. By combining plasticity and multimodality, HCIDL improves usability of user interfaces through adaptive behaviour by providing end-users with an interaction-set adapted to input/output of terminals and, an optimum layout. Keywords: Model driven engineering, Human-computer interface, User interface description languages, Multimodal applications, Plastic user interfaces

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

Development of construction specifications to attain clean rooms for the NOVA laser facility

International Nuclear Information System (INIS)

Benedix, C.P.

1980-02-01

This paper describes the process of defining technical requirements for a major Department of Energy Research and Development Facility and subsequent development of construction specifications for the clean spaces in that facility. The organizational interactions between technical client, Engineering and Construction elements are described. The importance of an interdisciplinary team approach is stressed. A brief description of the SHIVA Laser and NOVA Laser Clean Spaces is included to indicate the scope of the facility undertaking. A number of potential pitfalls are discussed that may be helpful to designers of new facilities

klax Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kprc Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

katl Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kmcn Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kogb Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kama Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ptkk Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kiwa Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kavp Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kdca Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kbwg Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kdfw Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kssi Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

pahn Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksrq Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kpvd Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kisp Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kttd Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

pmdy Terminal Aerodrome Forecast

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kmgm Terminal Aerodrome Forecast

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khib Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

pavd Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kfar Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kluk Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kwwr Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

klse Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksts Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

koth Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kbfl Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksgf Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

klch Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kpkb Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

krog Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kbjc Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksea Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kbwi Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kftw Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kpuw Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kabq Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksny Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

khio Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

klaf Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kfoe Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

ksmx Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kipt Terminal Aerodrome Forecast

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ktrk Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kwmc Terminal Aerodrome Forecast

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National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

katy Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

tjmz Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kdet Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kcxp Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

kbur Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...

krkd Terminal Aerodrome Forecast

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — TAF (terminal aerodrome forecast or terminal area forecast) is a format for reporting weather forecast information, particularly as it relates to aviation. TAFs are...