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Sample records for drying facility design

  1. Cold vacuum drying facility design requirements

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified

  2. Cold vacuum drying facility design requirements

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  3. Cold vacuum drying facility design requirements

    Energy Technology Data Exchange (ETDEWEB)

    Irwin, J.J.

    1997-09-24

    This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.

  4. Cold vacuum drying facility design requirements

    International Nuclear Information System (INIS)

    Irwin, J.J.

    1997-01-01

    This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility

  5. Cold vacuum drying facility 90% design review

    Energy Technology Data Exchange (ETDEWEB)

    O`Neill, C.T.

    1997-05-02

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

  6. Cold vacuum drying facility 90% design review

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

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

  7. Dry Well Storage Facility conceptual design study

    International Nuclear Information System (INIS)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included

  8. Dry Well Storage Facility conceptual design study

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included.

  9. Project W-441 cold vacuum drying facility design requirements document

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage

  10. Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    PIEPHO, M.G.

    1999-01-01

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR

  11. Cold Vacuum Drying facility design basis accident analysis documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

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

    International Nuclear Information System (INIS)

    HALLER, C.S.

    1999-01-01

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

  19. 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

  20. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    PITKOFF, C.C.

    1999-07-06

    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.

  2. Conceptual design and cost estimation of dry cask storage facility for spent fuel

    International Nuclear Information System (INIS)

    Maki, Yasuro; Hironaga, Michihiko; Kitano, Koichi; Shidahara, Isao; Shiomi, Satoshi; Ohnuma, Hiroshi; Saegusa, Toshiari

    1985-01-01

    In order to propose an optimum storage method of spent fuel, studies on the technical and economical evaluation of various storage methods have been carried out. This report is one of the results of the study and deals with storage facility of dry cask storage. The basic condition of this work conforms to ''Basic Condition for Spent Fuel Storage'' prepared by Project Group of Spent Fuel Dry Storage at July 1984. Concerning the structural system of cask storage facilities, trench structure system and concrete silo system are selected for storage at reactor (AR), and a reinforced concrete structure of simple design and a structure with membrance roof are selected for away from reactor (AFR) storage. The basic thinking of this selection are (1) cask is put charge of safety against to radioactivity and (2) storage facility is simplified. Conceptual designs are made for the selected storage facilities according to the basic condition. Attached facilities of storage yard structure (these are cask handling facility, cask supervising facility, cask maintenance facility, radioactivity control facility, damaged fuel inspection and repack facility, waste management facility) are also designed. Cost estimation of cask storage facility are made on the basis of the conceptual design. (author)

  3. 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.

  4. 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

  5. Cold Vacuum Drying Facility Condensate Collection System Design Description. System 19

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    2000-01-01

    The Cold Vacuum Drying (CVD) Facility of Spent Nuclear Fuel (SNF) provides required process systems, supporting equipment, and facilities to support the SNF Project mission. This system design description (SDD) addresses the Condensate Collection System (CCS). This is a general service system. The CCS begins at the condensate outlet of the general process air-handling unit (AHU) and the condensate outlets for the active process bays AHUs. The system terminates at each condensate collection tank (5 total)

  6. 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

  7. Cold Vacuum Drying Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Located near the K-Basins (see K-Basins link) in Hanford's 100 Area is a facility called the Cold Vacuum Drying Facility (CVDF).Between 2000 and 2004, workers at the...

  8. 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

  9. Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling 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) 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.

  10. Nitramine Drying & Fine Grinding Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Nitramine Drying and Fine Grinding Facility provides TACOM-ARDEC with a state-of-the-art facility capable of drying and grinding high explosives (e.g., RDX and...

  11. 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

  12. Cold Vacuum Drying facility personnel monitoring system design description (SYS 12); FINAL

    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

  13. Cold vacuum drying facility site evaluation report

    International Nuclear Information System (INIS)

    Diebel, J.A.

    1996-01-01

    In order to transport Multi-Canister Overpacks to the Canister Storage Building they must first undergo the Cold Vacuum Drying process. This puts the design, construction and start-up of the Cold Vacuum Drying facility on the critical path of the K Basin fuel removal schedule. This schedule is driven by a Tri-Party Agreement (TPA) milestone requiring all of the spent nuclear fuel to be removed from the K Basins by December, 1999. This site evaluation is an integral part of the Cold Vacuum Drying design process and must be completed expeditiously in order to stay on track for meeting the milestone

  14. 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

  15. Design of plutonium processing facilities

    International Nuclear Information System (INIS)

    Derbyshire, W.; Sills, R.J.

    1982-01-01

    Five considerations for the design of plutonium processing facilities are identified. These are: Toxicity, Radiation, Criticality, Containment and Remote Operation. They are examined with reference to reprocessing spent nuclear fuel and application is detailed both for liquid and dry processes. (author)

  16. Spent nuclear fuel project cold vacuum drying facility operations manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-05-12

    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.

  17. 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

  18. Cold Vacuum Drying Facility hazard analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Krahn, D.E.

    1998-02-23

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

  19. Cold Vacuum Drying Facility hazard analysis report

    International Nuclear Information System (INIS)

    Krahn, D.E.

    1998-01-01

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports

  20. Dry cleaning process in nuclear facilities

    International Nuclear Information System (INIS)

    Kizawa, Hideo; Nishihara, Yukio; Kohanawa, Osamu; Yamamoto, Masao.

    1985-01-01

    Purpose: To attain man-power saving and effective processing in the cleaning and administrating steps of working cloths in a radioactive material handling facility. Method: Radiation monitors, chute, conveying bags, storage lines, auxiliary charging chute, finishing equipments, automatic classifying circle conveyors and the likes are disposed to the up- and down-stream of a dry cleaner step, and the information processings and operation controls for each of the equipments are adapted to be carried out systematically. The specific items for the information to be handled are the amount of cloths to be cleaned, accumulation amount of conveying bags, operation states of the dry cleaner, contamination degree of cloths, operation states of the finishing equipments, storage amount of cloths in the storage area and the like. As the administrative function, administration of working cloths, control of secondary wastes, and preparation of operation recordings for each of the equipments are carried out. (Kamimura, M.)

  1. Design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

  2. Instrumentation Design and Development Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — RTTC has facilities for design, development and fabrication of: custominstrumentation, mobile instrumentation, miniaturized instrumentation, wirelessinstrumentation,...

  3. Criticality safety evaluation report for the cold vacuum drying facility's process water handling system

    International Nuclear Information System (INIS)

    NELSON, J.V.

    1999-01-01

    This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified

  4. 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

  5. Human factors engineering report for the cold vacuum drying facility

    Energy Technology Data Exchange (ETDEWEB)

    IMKER, F.W.

    1999-06-30

    The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF.

  6. Cold Vacuum Drying (CVD) Facility, Diesel Generator Fire Protection

    CERN Document Server

    Singh, G

    2000-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Fire Protection and Detection System installed by Project W-441 (Cold Vacuum Drying Facility and Diesel Generator Building) functions as required by project specifications.

  7. 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.

  8. Spent nuclear fuel project cold vacuum drying facility supporting data and calculation database

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-02-26

    This document provides a database of supporting calculations for the Cold Vacuum Drying Facility (CVDF). The database 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-002, 1997, ''Cold Vacuum Drying Facility Design Requirements'', Rev. 2, and the CVDF Summary Design Report. The database contains calculation report entries for all process, safety and facility systems in the CVDF, a general CVD operations sequence and the CVDF System Design Descriptions (SDDs). This database has been developed for the SNFP CVDF Engineering 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-02-03

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

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

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

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

  11. Designing a Distance Learning Facility.

    Science.gov (United States)

    Lambert, Michael P.

    1998-01-01

    Details the design of a distance-learning facility through analysis of its functions, paper-handling requirements, and current and future communications-technology needs. It also lists special features the facility should have, including up-to-date wiring capacities for telecommunications, uplink and downlink capabilities to satellites, and…

  12. Design & layout of recreation facilities

    Science.gov (United States)

    Howard R. Orr

    1971-01-01

    Design and layout of recreation facilities is a problem solving process that must be divorced from the emotionalism that has shrouded outdoor recreation and must deal deliberately with the growing information concerning people and natural resources.

  13. Production Facility SCADA Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Holloway, Michael Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baily, Scott A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wheat, Robert Mitchell Jr. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

  14. Design and Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Provides engineering design of aircraft components, subsystems and installations using Pro/E, Anvil 1000, CADKEY 97, AutoCAD 13. Engineering analysis tools include...

  15. Fire Hazard Analysis for the Cold Vacuum Drying (CVD) Facility

    International Nuclear Information System (INIS)

    JOHNSON, B.H.

    1999-01-01

    This Fire Hazard Analysis assesses the risk from fire within individual fire areas in the Cold Vacuum Drying Facility at the Hanford Site in relation to existing or proposed fire protection features to ascertain whether the objectives of DOE Order 5480.7A Fire Protection are met

  16. Fire Hazard Analysis for the Cold Vacuum Drying (CVD) Facility

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSON, B.H.

    1999-08-19

    This Fire Hazard Analysis assesses the risk from fire within individual fire areas in the Cold Vacuum Drying Facility at the Hanford Site in relation to existing or proposed fire protection features to ascertain whether the objectives of DOE Order 5480.7A Fire Protection are met.

  17. How do the work environment and work safety differ between the dry and wet kitchen foodservice facilities?

    OpenAIRE

    Chang, Hye-Ja; Kim, Jeong-Won; Ju, Se-Young; Go, Eun-Sun

    2012-01-01

    In order to create a worker-friendly environment for institutional foodservice, facilities operating with a dry kitchen system have been recommended. This study was designed to compare the work safety and work environment of foodservice between wet and dry kitchen systems. Data were obtained using questionnaires with a target group of 303 staff at 57 foodservice operations. Dry kitchen facilities were constructed after 2006, which had a higher construction cost and more finishing floors with ...

  18. Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

    International Nuclear Information System (INIS)

    KRAHN, D.E.

    2000-01-01

    The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt of multi-canister overpacks (MCOs) containing spent nuclear fuel. removal of free water from the MCOs using the cold vacuum drying process, and inerting and testing of the MCOs before transport to the Canister Storage Building. Controls required for public safety, significant defense in depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included

  19. Design Integration of Facilities Management

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2009-01-01

    One of the problems in the building industry is a limited degree of learning from experiences of use and operation of existing buildings. Development of professional facilities management (FM) can be seen as the missing link to bridge the gap between building operation and building design....... Strategies, methods and barriers for the transfer and integration of operational knowledge into the design process are discussed. Multiple strategies are needed to improve the integration of FM in design. Building clients must take on a leading role in defining and setting up requirements and procedures....... Involvement of professional facilities managers in the design process is an obvious strategy, but increased competences are needed among building clients, designers and the operational staff. More codification of operational knowledge is also needed, for instance in IT systems. The paper is based...

  20. Safety analysis report for the cold vacuum drying facility, phase 1, supporting civil/structural construction

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1998-01-01

    The Cold Vacuum Drying Facility is a subproject of the overall Spent Nuclear Fuel Project. This Phase 2 Safety Analysis Report incorporates the CVD systems design and will update the SAR per DOE Order 5480.23 for manual and other Hanford infrastructure changes

  1. System Configuration Management Implementation Procedure for the Cold Vacuum Drying Facility Monitoring and Control System

    International Nuclear Information System (INIS)

    ANGLESEY, M.O.

    2000-01-01

    The purpose of this document is to establish the System Configuration Management Implementation Procedure (SCMIP) for the Cold Vacuum Drying Facility (CVDF) Monitoring and Control System (MCS). This procedure provides configuration management for the process control system. The process control system consists of equipment hardware and software that controls and monitors the instrumentation and equipment associated with the CVDF processes. Refer to SNF-3090, Cold Vacuum Drying Facility Monitoring and Control System Design Description, HNF-3553, Annex B, Safety Analysis Report for the Cold Vacuum Drying Facility, and AP-CM-6-037-00, SNF Project Process Automation Software and Equipment Configuration. This SCMIP identifies and defines the system configuration items in the control system, provides configuration control throughout the system life cycle, provides configuration status accounting, physical protection and control, and verifies the completeness and correctness of these items

  2. Conceptual design report for the ICPP spent nuclear fuel dry storage project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    The conceptual design is presented for a facility to transfer spent nuclear fuel from shipping casks to dry storage containers, and to safely store those containers at ICPP at INEL. The spent fuels to be handled at the new facility are identified and overall design and operating criteria established. Physical configuration of the facility and the systems used to handle the SNF are described. Detailed cost estimate for design and construction of the facility is presented.

  3. DOE facilities solar design handbook

    Energy Technology Data Exchange (ETDEWEB)

    Hunn, Bruce D.; Balcomb, J. Douglas

    1978-01-01

    This handbook covers design of solar heating systems for commercial and laboratory buildings at Department of Energy Facilities. It includes discussions of solar energy fundamentals, solar heating and cooling technology, systems, and components, as well as a discussion of solar system economics. Quantitative analysis, with generalized design and sizing curves, is presented for solar heating so that collector and other system parameters can be cost-economically sized without a computer simulation. Solar system design considerations and guidelines, as well as guidelines for developing subsystem specifications, are presented. Thus this handbook is both a primer for the solar novice and a reference manual for the solar system designer.

  4. Facilities design for TIBER II

    International Nuclear Information System (INIS)

    Thomson, S.L.; Blevins, J.D.

    1987-01-01

    This paper describes the conceptual design of the reactor building and reactor maintenance building for the TIBER II tokamak. These buildings are strongly influenced by the reactor configuration, and their characterization allows a better understanding of the economic and technical implications of the reactor design. Key features of TIBER II that affect the facilities design are the small size and compact arrangement, the use of an external vacuum vessel, and the complete reliance on remote maintenance. The building design incorporates requirements for equipment layout, maintenance operations and equipment, safety, and contamination control. 4 figs

  5. Facility design, construction, and operation

    International Nuclear Information System (INIS)

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l'Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l'Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec's contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides' all of the basic information in these areas and reflects actual experience to date

  6. Facility design, construction, and operation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l`Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l`Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec`s contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides` all of the basic information in these areas and reflects actual experience to date.

  7. University of Wisconsin Oshkosh Anaerobic Dry Digestion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Koker, John [Univ. of Wisconsin, Oshkosh, WI (United States); Lizotte, Michael [Univ. of Wisconsin, Oshkosh, WI (United States)

    2017-02-08

    The University of Wisconsin Oshkosh Anaerobic Dry Digestion Facility is a demonstration project that supported the first commercial-scale use in the United States of high solids, static pile technology for anaerobic digestion of organic waste to generate biogas for use in generating electricity and heat. The research adds to the understanding of startup, operation and supply chain issues for anaerobic digester technology. Issues and performance were documented for equipment installation and modifications, feedstock availability and quality, weekly loading and unloading of digestion chambers, chemical composition of biogas produced, and energy production. This facility also demonstrated an urban industrial ecology approach to siting such facilities near sewage treatment plants (to capture and use excess biogas generated by the plants) and organic yard waste collection sites (a source of feedstock).

  8. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Master Equipment List

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-09-21

    This document provides the master equipment list (MEL) for the Cold Vacuum Drying Facility (CVDF). The MEL was prepared to comply with DOE Standard 3024-98, Content of System Design Descriptions. The MEL 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 and the CVDF System Design Descriptions (SDD). The MEL identifies the SSCs and their safety functions, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. The MEL also includes operating parameters, manufacturer information, and references the procurement specifications for the SSCs. This MEL shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR, the SDD's, and CVDF operations.

  9. Orientation to pollution prevention for facility design

    Energy Technology Data Exchange (ETDEWEB)

    Raney, E.A.; Whitehead, J.K.; Encke, D.B. [Westinghouse Hanford Co., Richland, WA (United States); Dorsey, J.A. [Kaiser Engineers Hanford Co., Richland, WA (United States)

    1994-01-01

    This material was developed to assist engineers in incorporating pollution prevention into the design of new or modified facilities within the U.S. Department of Energy (DOE). The material demonstrates how the design of a facility can affect the generation of waste throughout a facility`s entire life and it offers guidance on how to prevent the generation of waste during design. Contents include: Orientation to pollution prevention for facility design training course booklet; Pollution prevention design guideline; Orientation to pollution prevention for facility design lesson plan; Training participant survey and pretest; and Training facilitator`s guide and schedule.

  10. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

    Bohachek, Randy; Wallace, Bruce; Winston, Phil; Marschman, Steve

    2013-04-30

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  11. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

    Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

    2013-04-01

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  12. Force Dental Facility Design Guidance (AFDFDG)

    National Research Council Canada - National Science Library

    Kane, James

    1998-01-01

    This design guidance includes total USAF Dental Clinic facility space planning, construction criteria, and medical gases specification inclusive of architectural, mechanical, and electrical design requirements...

  13. National Ignition Facility system design requirements conventional facilities SDR001

    International Nuclear Information System (INIS)

    Hands, J.

    1996-01-01

    This System Design Requirements (SDR) document specifies the functions to be performed and the minimum design requirements for the National Ignition Facility (NIF) site infrastructure and conventional facilities. These consist of the physical site and buildings necessary to house the laser, target chamber, target preparation areas, optics support and ancillary functions

  14. Facility for washing and drying of multiwire chambers

    International Nuclear Information System (INIS)

    Kolachev, G.M.; Krotov, S.V.; Minakov, G.D.; Nikachalo, I.I.; Filimonov, G.S.

    1979-01-01

    A design of a special device for washing and drying multiwire chambers having an area of up to 1.5x2 m is described. The device consists of a heat-insulated ultrasonic bath and a 1.8 m 3 vacuum desiccator. The device reduces labour consumption when cleaning the chambers. For instance, it takes 1.5 h to wash a 88x86 cm chamber. Upon completion of washing and drying the chamber has the following characteristics: the efficiency plateau in the Ar+20% CO 2 mixture constitutes 200 V, while the noise level at the end of the efficiency plateau constitutes 5x10 -2 Hz/cm 2

  15. Ventilation design for new plutonium recovery facility

    International Nuclear Information System (INIS)

    Oliver, A.J.; Amos, C.L.

    1975-01-01

    In 1972 the Atomic Energy Commission (AEC) issued revised guidelines on ''Minimum Design Criteria for New Plutonium Facilities.'' With these criteria as guidelines, a new Plutonium Recovery Facility is being designed and constructed at the AEC Rocky Flats Plant. The methods by which the confinement of contamination and air treatment are being handled in this facility are described. (U.S.)

  16. Cold vacuum drying facility: Phase 1 FMEA/FMECA session report

    International Nuclear Information System (INIS)

    Pitkoff, C.

    1998-01-01

    The mission of the Spent Nuclear Fuel (SNF) Project is to remove the fuel currently located in the K-Basins 100 Area to provide safe handling and interim storage of the fuel. The spent nuclear fuel will be repackaged in multi-canister overpacks, partially dried in the Cold Vacuum Drying Facility (CVDF), and then transported to the Canister Storage Building (CSB) for further processing and interim storage. The CVDF, a subproject to the SNF Project, will be constructed in the 100K area. The CVDF will remove free water and vacuum dry the spent nuclear fuel, making it safer to transport and store at the CSB. At present, the CVDF is approximately 90% complete with definitive design. Part of the design process is to conduct Failure Modes, Effects, and Criticality Analysis (FMECA). A four-day FMECA session was conducted August 18 through 21, 1997. The purpose of the session was to analyze 16 subsystems and operating modes to determine consequences of normal, upset, emergency, and faulted conditions with respect to production and worker safety. During this process, acceptable and unacceptable risks, needed design or requirement changes, action items, issues/concerns, and enabling assumptions were identified and recorded. Additionally, a path forward consisting of recommended actions would be developed to resolve any unacceptable risks. The team consisted of project management, engineering, design authority, design agent, safety, operations, and startup personnel. The report summarizes potential problems with the designs, design requirements documentation, and other baseline documentation

  17. AERIAL DELIVERY DESIGN AND FABRICATION FACILITY

    Data.gov (United States)

    Federal Laboratory Consortium — Skilled personnel are equipped to design and develop various prototype airdrop items. This facility has all classes of sewing machines, ranging from lightweight to...

  18. Spent nuclear fuel project cold vacuum drying facility safety equipment list

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-02-24

    This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved.

  19. Spent nuclear fuel project cold vacuum drying facility safety equipment list

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved

  20. Conceptual design of repository facilities

    International Nuclear Information System (INIS)

    Beale, H.; Engelmann, H.J.; Souquet, G.; Mayence, M.; Hamstra, J.

    1980-01-01

    As part of the European Economic Communities programme of research into underground disposal of radioactive wastes repository design studies have been carried out for application in salt deposits, argillaceous formations and crystalline rocks. In this paper the design aspects of repositories are reviewed and conceptual designs are presented in relation to the geological formations under consideration. Emphasis has been placed on the disposal of vitrified high level radioactive wastes although consideration has been given to other categories of radioactive waste

  1. Design Standards for School Art Facilities

    Science.gov (United States)

    National Art Education Association, 2015

    2015-01-01

    "Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

  2. Construction of water intake facilities from partially drying up watercourses

    Directory of Open Access Journals (Sweden)

    Orlov Evgeniy Vladimirovich

    Full Text Available Partially ephemeral streams are complex objects that can still be used for water supply or irrigation of agricultural land. The problem of such streams is poorly studied, because the influence of various environmental factors complicates carrying out any experiments. Also it is not possible to make their full classification due to their very strong variability not only on a particular geographical belt, but also within separate areas of the river. All this undoubtedly complicates the task of the designers when designing the system. Creation of laboratory models, allowing us to evaluate the possibilities of a spring use for the purpose of water supply, is very promising. These watercourses have a large amount of suspended sediments, so it is not possible to use the standard scheme of water using of the coastal and fluvial water intake structures. It is proposed to organize the fight with the sediments in the flow chart of primary clarifiers, which will perform the function of settling suspensions, to facilitate the work of water treatment facilities. Also the creation of artificial prop is useful in order to achieve the required level of water in a watercourse for water organization. If under the bottom of the river there is underground water, and the permeability of the soil is good, it is possible to arrange the withdrawal of water through infiltration intakes, by setting the filter under the bottom of the watercourse with its connection to filter, from which the water will climb to submersible pumps. Additional filtration through the soil of the river bottom allows not using the scheme sumps, which significantly reduces the cost of epy incoming water treatment.

  3. 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

  4. Designing CAF-adjuvanted dry powder vaccines: Spray drying preserves the adjuvant activity of CAF01

    DEFF Research Database (Denmark)

    Ingvarsson, Pall Thor; Schmidt, Signe Tandrup; Christensen, Dennis

    2013-01-01

    spray drying. The optimal excipient to stabilize CAF01 during spray drying and for the design of nanocomposite microparticles was identified among mannitol, lactose and trehalose. Trehalose and lactose were promising stabilizers with respect to preserving liposome size, as compared to mannitol...

  5. A new framework to assess risk for a spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Ryu, J. H.; Jae, M. S.; Jung, C. W.

    2004-01-01

    A spent fuel dry storage facility is a dry cooling storage facility for storing irradiated nuclear fuel and associated radioactive materials. It has very small possibilities to release radiation materials. It means a safety analysis for a spent fuel dry storage facility is required before construction. In this study, a new framework for assessing risk associated with a spent fuel dry storage facility is represented. A safety assessment framework includes 3 modules such as assessment of basket/cylinder failure rates, that of overall storage system, and site modeling. A reliability physics model for failure rates, event tree analysis(ETA)/fault tree analysis for system analysis, Bayesian analysis for initial events data, and MACCS code for consequence analysis have been used in this study

  6. Institutionalizing Safeguards By Design for Nuclear Facilities

    International Nuclear Information System (INIS)

    Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

    2008-01-01

    Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

  7. Design of an experimental set up for convective drying: experimental studies at different drying temperature

    Science.gov (United States)

    Mohan, V. P. Chandra; Talukdar, Prabal

    2013-01-01

    An experimental setup is designed to investigate the convective drying of moist object experimentally. All the design data, components of setup, materials and specifications are presented. Transient moisture content of a rectangular shaped potato slice (4 × 2 × 2 cm) is measured at different air temperatures of 40, 50, 60 and 70 °C with an air velocity of 2 m/s. Two different drying rate periods are observed. Results are compared with available results from literature.

  8. Interior Design Factors in Library Facilities.

    Science.gov (United States)

    Jackson, Patricia Ann

    When planning the interior of a library facility, the planning team of librarian, library consultant, architect, and interior design consultant must focus attention on the basic principles of interior design and the psychological needs of the user. Colors for an interior should be selected with careful regard to space, light, and emotional and…

  9. Landfill gas management facilities design guidelines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-03-15

    In British Columbia, municipal solid waste landfills generate over 1000 tonnes of methane per year; landfill gas management facilities are required to improve the environmental performance of solid waste landfills. The aim of this document, developed by the British Columbia Ministry of the Environment, is to provide guidance for the design, installation, and operation of landfill gas management facilities to address odor and pollutant emissions issues and also address health and safety issues. A review of technical experience and best practices in landfill gas management facilities was carried out, as was as a review of existing regulations related to landfill gas management all over the world. This paper provides useful information to landfill owners, operators, and other professionals for the design of landfill gas management facilities which meet the requirements of landfill gas management regulations.

  10. UTN's gamma irradiation facility: design and concept

    International Nuclear Information System (INIS)

    Mohamad Noor Mohamad Yunus

    1986-01-01

    UTN is building a multipurpose gamma irradiation facility which compromises of research and pilot scale irradiation cells in The Fifth Malaysia Plan. The paper high-lights the basic futures of the facility in terms of its design and selection including layout sketches. Plant performances and limitations are discussed. Plants safety is briefly highlighted in block diagrams. Lastly, a typical specification brief is tabled in appendix for reference purposes. (author)

  11. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to

  12. Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Philip C. Durst

    2012-05-01

    This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA) of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement with

  13. Comparison between mobile VR services and central VR service facility for dry active waste

    International Nuclear Information System (INIS)

    Dam, A.S.; Bradley, M.J.

    1985-01-01

    Low-level radioactive dry wastes can be volume reduced using either mobile or central facilities with super-compactors, or incinerators, or both. This paper compares the technical, operational and economic factors for mobile versus central facilities. Analyses indicated that customer costs, in addition to the service vendors' fee, are a significant factor in the evaluation of mobile services. The most attractive option is a central facility offering both incineration and super-compaction

  14. Criticality safety and facility design considerations

    International Nuclear Information System (INIS)

    Waltz, W.R.

    1991-06-01

    Operations with fissile material introduce the risk of a criticality accident that may be lethal to nearby personnel. In addition, concerns over criticality safety can result in substantial delays and shutdown of facility operations. For these reasons, it is clear that the prevention of a nuclear criticality accident should play a major role in the design of a nuclear facility. The emphasis of this report will be placed on engineering design considerations in the prevention of criticality. The discussion will not include other important aspects, such as the physics of calculating limits nor criticality alarm systems

  15. Conceptual design study advanced concepts test (ACT) facility

    Energy Technology Data Exchange (ETDEWEB)

    Zaloudek, F.R.

    1978-09-01

    The Advanced Concepts Test (ACT) Project is part of program for developing improved power plant dry cooling systems in which ammonia is used as a heat transfer fluid between the power plant and the heat rejection tower. The test facility will be designed to condense 60,000 lb/hr of exhaust steam from the No. 1 turbine in the Kern Power Plant at Bakersfield, CA, transport the heat of condensation from the condenser to the cooling tower by an ammonia phase-change heat transport system, and dissipate this heat to the environs by a dry/wet deluge tower. The design and construction of the test facility will be the responsibility of the Electric Power Research Institute. The DOE, UCC/Linde, and the Pacific Northwest Laboratories will be involved in other phases of the project. The planned test facilities, its structures, mechanical and electrical equipment, control systems, codes and standards, decommissioning requirements, safety and environmental aspects, and energy impact are described. Six appendices of related information are included. (LCL)

  16. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. [Argonne National Lab., IL (United States); Zhang, Z.Y. [Polytechnic Univ., Brooklyn, NY (United States); Myers, G.; Cvercko, A. [Sterling Engineering, Westchester, IL (United States); Williams, J.R. [Alfred Benesch and Co., Chicago, IL (United States)

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  17. Designing Animation Facilities for gCSP

    NARCIS (Netherlands)

    van der Steen, T.T.J.; Groothuis, M.A.; Broenink, Johannes F.

    To improve feedback on how concurrent CSP-based programs run, the graphical CSP design tool has been extended with animation facilities. The state of processes, constructs, and channel ends are indicated with colours both in the gCSP diagrams and in the composition tree (hierarchical tree showing

  18. State-of-the-art dry active waste processing facility

    International Nuclear Information System (INIS)

    Hillmer, T.; Ingalsbe, H.; Alcorn, G.; Anderson, K.; Dahlen, D.

    1989-01-01

    Palo Verde Nuclear Generating Station (PVNGS) is operated by Arizona Public Service for a consortium of seven owners. The site consists of three identical single unit power plants. Each unit is a Combustion Engineering Series 80 pressurized water reactor (PWR) rated at 1270 Megawatts electric. The site is located 100 kilometers west of Phoenix, Arizona in the arid southwest desert region of the United States of America. Since the start up of Unit One in 1985, Palo Verde has aggressively pursued waste volume reduction. This includes a dry active waste (DAW) segregation program that locates and separates nonradioactive and reusable materials that have been mixed with the radioactive DAW. The DAW program is described in further detail in the paper

  19. Monitored retrievable storage facility conceptual design

    International Nuclear Information System (INIS)

    Stringer, J.B.

    1994-01-01

    The United States Congress has enacted legislation directing the Department of Energy to take title to and dispose of high level nuclear waste. As part of a contract which resulted from this act, a conceptual design for a Monitored Retrievable Storage facility has been completed. This paper presents the results of that conceptual design. Six design concepts were investigated for handling and storing spent nuclear fuel assemblies from commercial reactors. All six of these design concepts satisfy program requirements and provide safe and efficient methods to handle and store spent nuclear fuel. Provided in this paper is an overview of the basis for conceptual design, a discussion of the function and purpose of the MRS, schedule information, and discussions of the six design concepts. This conceptual design is an important step towards furthering the civilian radioactive waste management system program. (author). 2 figs, 1 tab

  20. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Bong Shick; Kim, Y. S.; Lee, C. Y. and others

    1999-03-01

    The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and fabrication of main equipment, licensing and technical review for fuel test loop have been performed during 2 years(1997, 1998) for this project. Following contents are described in the report. - Procurement and fabrication of the equipment, piping for OPS - IPS manufacture - License - Technical review and evaluation of the FTL facility. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and review ofHANARO interface have been performed respectively. (author)

  1. Preliminary Design of the AEGIS Test Facility

    CERN Document Server

    Dassa, Luca; Cambiaghi, Danilo

    2010-01-01

    The AEGIS experiment is expected to be installed at the CERN Antiproton Decelerator in a very close future, since the main goal of the AEGIS experiment is the measurement of gravity impact on antihydrogen, which will be produced on the purpose. Antihydrogen production implies very challenging environmental conditions: at the heart of the AEGIS facility 50 mK temperature, 1e-12 mbar pressure and a 1 T magnetic field are required. Interfacing extreme cryogenics with ultra high vacuum will affect very strongly the design of the whole facility, requiring a very careful mechanical design. This paper presents an overview of the actual design of the AEGIS experimental facility, paying special care to mechanical aspects. Each subsystem of the facility – ranging from the positron source to the recombination region and the measurement region – will be shortly described. The ultra cold region, which is the most critical with respect to the antihydrogen formation, will be dealt in detail. The assembly procedures will...

  2. Fluid dynamics simulation for design on sludge drying equipment

    Science.gov (United States)

    Li, Shuiping; Liang, Wang; Kai, Zhang

    2017-10-01

    Sludge drying equipment is a key component in the sludge drying disposal, the structure of drying equipment directly affects the drying disposal of the sludge, so it is necessary to analyse the performance of the drying equipment with different structure. Fluent software can be very convenient to get the distribution of the flow field and temperature field inside the drying equipment which reflects the performance of the structure. In this paper, the outlet position of the sludge and the shape of the sludge inlet are designed. The geometrical model of the drying equipment is established by using pre-processing software Gambit, and the meshing of the model is carried out. The Eulerian model is used to simulate the flow of each phase and the interaction between them, and the realizable turbulence model is used to simulate the turbulence of each phase. Finally, the simulation results of the scheme are compared and the optimal structure scheme is obtained, the operational requirement is proposed. The CFD theory provides a reliable basis for the drying equipment research and reduces the time and costs of the research.

  3. Analysis for seismic response of dry storage facility for spent fuel

    International Nuclear Information System (INIS)

    Ko, Y.-Y.; Hsu, S.-Y.; Chen, C.-H.

    2009-01-01

    Most of the dry storage systems for spent fuel are freestanding, which leads to stability concerns in an earthquake. In this study, as a safety check, the ABAQUS/Explicit code is adopted to analyse the seismic response of the dry storage facility planned to be installed at Nuclear Power Plant no. 1 (NPP1) in Taiwan. A 3D coupled finite element (FE) model was established, which consisted of a freestanding cask, a concrete pad, and underneath soils interacting with frictional contact interfaces. The scenario earthquake used in the model included an artificial earthquake compatible to the design spectrum of NPP1, and a strong ground motion modified from the time history recorded during the Chi-Chi earthquake. The results show that the freestanding cask will slide, but not tip over, during strong earthquakes. The scale of the sliding is very small and a collision between casks will not occur. In addition, the differential settlement of the foundation pad that takes place due to the weight of the casks increases the sliding potential of the casks during earthquakes

  4. Shielding design for positron emission tomography facility

    International Nuclear Information System (INIS)

    Abdallah, I.I.

    2007-01-01

    With the recent advent of readily available tracer isotopes, there has been marked increase in the number of hospital-based and free-standing positron emission tomography (PET) clinics. PET facilities employ relatively large activities of high-energy photon emitting isotopes, which can be dangerous to the health of humans and animals. This coupled with the current dose limits for radiation worker and members of the public can result in shielding requirements. This research contributes to the calculation of the appropriate shielding to keep the level of radiation within an acceptable recommended limit. Two different methods were used including measurements made at selected points of an operating PET facility and computer simulations by using Monte Carlo Transport Code. The measurements mainly concerned the radiation exposure at different points around facility using the survey meter detectors and Thermoluminescent Dosimeters (TLD). Then the set of manual calculation procedures were used to estimate the shielding requirements for a newly built PEF facility. The results from the measurement and the computer simulation were compared to the results obtained from the set manual calculation procedure. In general, the estimated weekly dose at the points of interest is lower than the regulatory limits for the little company of Mary Hospital. Furthermore, the density and the HVL for normal strength concrete and clay bricks are almost similar. In conclusion, PET facilities present somewhat different design requirements and are more likely to require additional radiation shielding. Therefore, existing shields at the little Company of Mary Hospital are in general found to be adequate and satisfactory and additional shielding was found necessary at the new PET facility in the department of Nuclear Medicine of the Dr. George Mukhari Hospital. By use of appropriate design, by implying specific shielding requirements and by maintaining good operating practices, radiation doses to

  5. Design, Construction and Testing of a Dry Sand Sieving Machine ...

    African Journals Online (AJOL)

    This paper reports on the design, construction and Testing of a dry sand sieving machine. The sample to be sieved is uniformly graded. The coefficient of uniformity is 1.11, thus the machine design does not sieve larger particles such as gravel. The slip calculated is 36% which enabled the proper configuration of the V-belt.

  6. Conceptual design of the National Ignition Facility

    International Nuclear Information System (INIS)

    Paisner, J.A.; Kumpan, S.A.; Lowdermilk, W.H.; Boyes, J.D.; Sorem, M.

    1995-01-01

    DOE commissioned a Conceptual Design Report (CDR) for the National Ignition Facility (NIF) in January 1993 as part of a Key Decision Zero (KDO), justification of Mission Need. Motivated by the progress to date by the Inertial Confinement Fusion (ICF) program in meeting the Nova Technical Contract goals established by the National Academy of Sciences in 1989, the Secretary requested a design using a solid-state laser driver operating at the third harmonic (0.35 μm) of neodymium (Nd) glass. The participating ICF laboratories signed a Memorandum of Agreement in August 1993, and established a Project organization, including a technical team from the Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the Laboratory for Laser Energetics at the University of Rochester. Since then, we completed the NIF conceptual design, based on standard construction at a generic DOE Defense Program's site, and issued a 7,000-page, 27-volume CDR in May 1994.2 Over the course of the conceptual design study, several other key documents were generated, including a Facilities Requirements Document, a Conceptual Design Scope and Plan, a Target Physics Design Document, a Laser Design Cost Basis Document, a Functional Requirements Document, an Experimental Plan for Indirect Drive Ignition, and a Preliminary Hazards Analysis (PHA) Document. DOE used the PHA to categorize the NIF as a low-hazard, non-nuclear facility. On October 21, 1994 the Secretary of Energy issued a Key Decision One (KD1) for the NIF, which approved the Project and authorized DOE to request Office of Management and Budget-approval for congressional line-item FY 1996 NIF funding for preliminary engineering design and for National Environmental Policy Act activities. In addition, the Secretary declared Livermore as the preferred site for constructing the NIF. The Project will cost approximately $1.1 billion and will be completed at the end of FY 2002

  7. Design of Tomato Drying System by Utilizing Brine Geothermal

    Science.gov (United States)

    Afuar, W.; Sibarani, B.; Abdurrahman, G.; Hendrarsakti, J.

    2016-09-01

    Cultivation of tomato plants in Indonesia has been started since 1961.Tomatoes generally will rot in three days if left on storage. Moreover, low quality tomatoes have cheaper price. After harvested, tomatoes need to be treated by drying process so it can last longer. Energy for drying tomatoes can be obtained by utilizing heat from geothermal brine. Purpose of this research is to design a tomato drying system by extracting heat of geothermal brine from separator with certain flow rate to heat up water by using a heat exchanger. Furthermore, this water will be used to heat up the surrounding air which is circulated by blower system to heat up the tomatoes chamber. Tomatoes drying process needs temperature range of 50-70°C to evaporate water content from 95.7% to 26%. After that treatment, the tomatoes are expected to have better durability. The objective of this study is to determine the quantity of hot brine which is needed for drying tomatoes and to design a drying system so that tomatoes can last longer.

  8. Dry transfer system for spent fuel: Project report, A system designed to achieve the dry transfer of bare spent fuel between two casks. Final report

    International Nuclear Information System (INIS)

    Dawson, D.M.; Guerra, G.; Neider, T.; Shih, P.

    1995-12-01

    This report describes the system developed by EPRI/DOE for the dry transfer of spent fuel assemblies outside the reactor spent fuel pool. The system is designed to allow spent fuel assemblies to be removed from a spent fuel pool in a small cask, transported to the transfer facility, and transferred to a larger cask, either for off-site transportation or on-site storage. With design modifications, this design is capable of transferring single spent fuel assemblies from dry storage casks to transportation casks or visa versa. One incentive for the development of this design is that utilities with limited lifting capacity or other physical or regulatory constraints are limited in their ability to utilize the current, more efficient transportation and storage cask designs. In addition, DOE, in planning to develop and implement the multi-purpose canister (MPC) system for the Civilian Radioactive Waste Management System, included the concept of an on-site dry transfer system to support the implementation of the MPC system at reactors with limitations that preclude the handling of the MPC system transfer casks. This Dry Transfer System can also be used at reactors wi decommissioned spent fuel pools and fuel in dry storage in non-MPC systems to transfer fuel into transportation casks. It can also be used at off-reactor site interim storage facilities for the same purpose

  9. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

  10. Large coil test facility instrumentation system design

    International Nuclear Information System (INIS)

    Walstrom, P.L.; Fletcher, W.M.; Goddard, J.S.; Murphy, J.L.

    1979-01-01

    The design of the instrumentation system for the Large Coil Test Facility (LCTF) is described. Sensors are divided into two categories: coil diagnostic sensors, installed in the test coils; and facility sensors, installed in the various systems of the test facility in order to monitor their performance. After signal conditioning, data from the ''fast'' channels are multiplexed, digitized, and stored in four microcomputer systems programmed to be used in a ring buffer mode to record data before and after receipt of a random trigger from the normal zone detection circuitry. ''Slow'' channels are digitized by a scanner and buffered by a microcomputer. Selected data channels are continuously displayed on digital or recorded on strip chart recorders. The microcomputer systems are interfaced to a central minicomputer system for display and archival storage. Facility variables are digitized by a separate scanner system. Certain critical fault variables are compared with set point values, and if they are out of range, cause a programmable logic controller to initiate an emergency coil energy dump. 2 refs

  11. Fermilab HEPCloud Facility Decision Engine Design

    Energy Technology Data Exchange (ETDEWEB)

    Tiradani, Tiradani,Anthony [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Altunay, Mine [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Dagenhart, David [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Kowalkowski, Jim [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Litvintsev, Dmitry [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Lu, Qiming [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Mhashilkar, Parag [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Moibenko, Alexander [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Paterno, Marc [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Timm, Steven [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2017-05-23

    The Decision Engine is a critical component of the HEP Cloud Facility. It provides the functionality of resource scheduling for disparate resource providers, including those which may have a cost or a restricted allocation of cycles. Along with the architecture, design, and requirements for the Decision Engine, this document will provide the rationale and explanations for various design decisions. In some cases, requirements and interfaces for a limited subset of external services will be included in this document. This document is intended to be a high level design. The design represented in this document is not complete and does not break everything down in detail. The class structures and pseudo-code exist for example purposes to illustrate desired behaviors, and as such, should not be taken literally. The protocols and behaviors are the important items to take from this document. This project is still in prototyping mode so flaws and inconsistencies may exist and should be noted and treated as failures.

  12. Integrated safeguards and facility design and operations

    International Nuclear Information System (INIS)

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

  13. JPL Facilities and Software for Collaborative Design: 1994 - Present

    Science.gov (United States)

    DeFlorio, Paul A.

    2004-01-01

    The viewgraph presentation provides an overview of the history of the JPL Project Design Center (PDC) and, since 2000, the Center for Space Mission Architecture and Design (CSMAD). The discussion includes PDC objectives and scope; mission design metrics; distributed design; a software architecture timeline; facility design principles; optimized design for group work; CSMAD plan view, facility design, and infrastructure; and distributed collaboration tools.

  14. Extended Dry Storage Signature Bench Scale Detector Conceptual Design

    Energy Technology Data Exchange (ETDEWEB)

    Rauch, Eric Benton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-02

    This report is the conceptual design of a detector based on research within the Extended Dry Storage Signature Development project under the DOE-­NE MPACT campaign. This is the second year of the project; from this year’s positive results, the next step is building a prototype and testing with real materials .

  15. How do the work environment and work safety differ between the dry and wet kitchen foodservice facilities?

    Science.gov (United States)

    Chang, Hye-Ja; Kim, Jeong-Won; Ju, Se-Young; Go, Eun-Sun

    2012-08-01

    In order to create a worker-friendly environment for institutional foodservice, facilities operating with a dry kitchen system have been recommended. This study was designed to compare the work safety and work environment of foodservice between wet and dry kitchen systems. Data were obtained using questionnaires with a target group of 303 staff at 57 foodservice operations. Dry kitchen facilities were constructed after 2006, which had a higher construction cost and more finishing floors with anti-slip tiles, and in which employees more wore non-slip footwear than wet kitchen (76.7%). The kitchen temperature and muscular pain were the most frequently reported employees' discomfort factors in the two systems, and, in the wet kitchen, "noise of kitchen" was also frequently reported as a discomfort. Dietitian and employees rated the less slippery and slip related incidents in dry kitchens than those of wet kitchen. Fryer area, ware-washing area, and plate waste table were the slippery areas and the causes were different between the functional areas. The risk for current leakage was rated significantly higher in wet kitchens by dietitians. In addition, the ware-washing area was found to be where employees felt the highest risk of electrical shock. Muscular pain (72.2%), arthritis (39.1%), hard-of-hearing (46.6%) and psychological stress (47.0%) were experienced by employees more than once a month, particularly in the wet kitchen. In conclusion, the dry kitchen system was found to be more efficient for food and work safety because of its superior design and well managed practices.

  16. Comparison of different designs of bottom linings with dry joints

    OpenAIRE

    Gasser, A.; Rekik, A.; Blond, E.; Andreev, K.

    2011-01-01

    International audience; Many bottom linings of refractory structures used in steel making industry are made of masonries with or without mortar. Several designs are possible: parallel, fish bone or radial. To compare the influence of these designs on the maximum stresses in the steel shell, the masonry with dry joints was modelled by a homogeneous equivalent material that takes into account the possibility of joint closure. The thermo-mechanical properties of this equivalent material were det...

  17. Equipment designs for the spent LWR fuel dry storage demonstration

    International Nuclear Information System (INIS)

    Steffen, R.J.; Kurasch, D.H.; Hardin, R.T.; Schmitten, P.F.

    1980-01-01

    In conjunction with the Spent Fuel Handling and Packaging Program (SFHPP) equipment has been designed, fabricated and successfully utilized to demonstrate the packaging and interim dry storage of spent LWR fuel. Surface and near surface storage configurations containing PWR fuel assemblies are currently on test and generating baseline data. Specific areas of hardware design focused upon include storage cell components and the support related equipment associated with encapsulation, leak testing, lag storage, and emplacement operations

  18. Design of the MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Johnson, J.V.; Brabazon, E.J.

    2001-01-01

    A consortium of Duke Engineering and Services, Inc., COGEMA, Inc. and Stone and Webster (DCS) are designing a mixed oxide fuel fabrication facility (MFFF) for the U.S. Department of Energy (DOE) to convert surplus plutonium to mixed oxide (MOX) fuel to be irradiated in commercial nuclear power plants based on the proven European technology of COGEMA and BELGONUCLEAIRE. This paper describes the MFFF processes, and how the proven MOX fuel fabrication technology is being adapted as required to comply with U.S. requirements. (author)

  19. Safety analysis report for the Cold Vacuum Drying Facility, phase 1, supporting civil/structural construction

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1997-01-01

    The US Department of Energy established the K Basins Spent Nuclear Fuel Project to address safety and environmental concerns associated with deteriorating spent nuclear fuel presently stored under water in the Hanford Site's K Basins, which are located near the Columbia River. Recommendations for a series of aggressive projects to construct and operate systems and facilities to manage the safe removal of K Basins fuel were made in WHC-EP-0830, Hanford Spent Nuclear Fuel Recommended Path Forward,' and its subsequent update, WHC-SD-SNF-SP-005, Hanford Spent Nuclear Fuel Project Integrated Process Strategy for K Basins Fuel. The integrated process strategy recommendations include the following process steps: fuel preparation activities at the K Basins, including removing the fuel elements from their K Basin canisters, separating fuel particulate from fuel elements and fuel fragments greater than 0.6 cm (0.25 in.) in any dimension, removing excess sludge from the fuel and fuel fragments by means of flushing, as necessary, and packaging the fuel into multicanister overpacks; removal of free water by draining and vacuum drying at the Cold Vacuum Drying Facility (CVDF), a new facility in the 100 K Area of the Hanford Site. This report is contains the safety analysis for the Cold Vacuum Drying Facility, Phase 1

  20. Design, fabrication and installation of irradiation facilities

    International Nuclear Information System (INIS)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C.

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs

  1. Fusion Development Facility Machine Design Aspects

    Science.gov (United States)

    Smith, J. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, R. D.; Wong, C. P. C.

    2008-11-01

    To fill the gap prior to building a fusion demonstration power plant (DEMO), a Fusion Development Facility (FDF) is proposed. As currently configured, FDF is a copper, water-cooled coil machine capable of running continuously for several weeks with the goal to test several blanket configurations in its lifetime. To accommodate multiple changes in blankets, a machine configuration must be chosen that allows for the efficient remote exchange. The TF coil configuration drives the primary maintenance approach decision. A TF coil with joints similar to DIII-D and Alcator C-Mod, allows for one maintenance approach while a continuously wound TF coil drives a different approach. The base machine design parameters are described. The different machine configuration options are presented which consider the design aspects for the machine including alignment of the first wall and divertor, coolant access, and exchange of the blanket.

  2. Fire Hazard Analysis for the Cold Vacuum Drying facility (CVD) Facility

    International Nuclear Information System (INIS)

    SINGH, G.

    2000-01-01

    The CVDF is a nonreactor nuclear facility that will process the Spent Nuclear Fuels (SNF) presently stored in the 105-KE and 105-KW SNF storage basins. Multi-canister overpacks (MCOs) will be loaded (filled) with K Basin fuel transported to the CVDF. The MCOs will be processed at the CVDF to remove free water from the fuel cells (packages). Following processing at the CVDF, the MCOs will be transported to the CSB for interim storage until a long-term storage solution can be implemented. This operation is expected to start in November 2000. A Fire Hazard Analysis (FHA) is required for all new facilities and all nonreactor nuclear facilities, in accordance with U.S. Department of Energy (DOE) Order 5480.7A, Fire Protection. This FHA has been prepared in accordance with DOE 5480.7A and HNF-PRO-350, Fire Hazard Analysis Requirements. Additionally, requirements or criteria contained in DOE, Richland Operations Office (RL) RL Implementing Directive (RLID) 5480.7, Fire Protection, or other DOE documentation are cited, as applicable. This FHA comprehensively assesses the risk of fire at the CVDF to ascertain whether the specific objectives of DOE 5480.7A are met. These specific fire protection objectives are: (1) Minimize the potential for the occurrence of a fire. (2) Ensure that fire does not cause an onsite or offsite release of radiological and other hazardous material that will threaten the public health and safety or the environment. (3) Establish requirements that will provide an acceptable degree of life safety to DOE and contractor personnel and ensure that there are no undue hazards to the public from fire and its effects in DOE facilities. (4) Ensure that vital DOE programs will not suffer unacceptable delays as a result of fire and related perils. (5) Ensure that property damage from fire and related perils does not exceed an acceptable level. (6) Ensure that process control and safety systems are not damaged by fire or related perils. This FHA is based on the

  3. Fire Hazard Analysis for the Cold Vacuum Drying facility (CVD) Facility

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-09-06

    The CVDF is a nonreactor nuclear facility that will process the Spent Nuclear Fuels (SNF) presently stored in the 105-KE and 105-KW SNF storage basins. Multi-canister overpacks (MCOs) will be loaded (filled) with K Basin fuel transported to the CVDF. The MCOs will be processed at the CVDF to remove free water from the fuel cells (packages). Following processing at the CVDF, the MCOs will be transported to the CSB for interim storage until a long-term storage solution can be implemented. This operation is expected to start in November 2000. A Fire Hazard Analysis (FHA) is required for all new facilities and all nonreactor nuclear facilities, in accordance with U.S. Department of Energy (DOE) Order 5480.7A, Fire Protection. This FHA has been prepared in accordance with DOE 5480.7A and HNF-PRO-350, Fire Hazard Analysis Requirements. Additionally, requirements or criteria contained in DOE, Richland Operations Office (RL) RL Implementing Directive (RLID) 5480.7, Fire Protection, or other DOE documentation are cited, as applicable. This FHA comprehensively assesses the risk of fire at the CVDF to ascertain whether the specific objectives of DOE 5480.7A are met. These specific fire protection objectives are: (1) Minimize the potential for the occurrence of a fire. (2) Ensure that fire does not cause an onsite or offsite release of radiological and other hazardous material that will threaten the public health and safety or the environment. (3) Establish requirements that will provide an acceptable degree of life safety to DOE and contractor personnel and ensure that there are no undue hazards to the public from fire and its effects in DOE facilities. (4) Ensure that vital DOE programs will not suffer unacceptable delays as a result of fire and related perils. (5) Ensure that property damage from fire and related perils does not exceed an acceptable level. (6) Ensure that process control and safety systems are not damaged by fire or related perils. This FHA is based on the

  4. Optimization design of solar enhanced natural draft dry cooling tower

    International Nuclear Information System (INIS)

    Zou, Zheng; Guan, Zhiqiang; Gurgenci, Hal

    2013-01-01

    Highlights: • We proposed a cost model for solar enhanced natural draft dry cooling tower. • We proposed an optimization scheme for this new cooling system. • We optimally designed one for a 50 MW EGS geothermal plant as a demonstration. • Results proved its economic advantages for EGS geothermal application. - Abstract: This paper proposed an optimization scheme for solar enhanced natural draft dry cooling tower design, in which a detailed cost model was proposed including capital, labour, maintenance and operation costs of each component. Based on the developed cost model, the optimal design option can be identified in terms of the relatively lower annual cost and the relatively higher total extra income over the Solar Enhanced Natural Draft Dry Cooling Tower (SENDDCT) lifetime. As a case study, a SENDDCT was optimally designed to meet the cooling demand for a 50 MW geothermal power plant with Engineered Geothermal System (EGS) technology. The results showed that the optimized SENDDCT not only has better cooling performance during the daytime but also is a cost effective option for EGS geothermal power plants

  5. Fire Hazard Analysis for the Cold Vacuum Drying facility (CVD) Facility

    CERN Document Server

    Singh, G

    2000-01-01

    The CVDF is a nonreactor nuclear facility that will process the Spent Nuclear Fuels (SNF) presently stored in the 105-KE and 105-KW SNF storage basins. Multi-canister overpacks (MCOs) will be loaded (filled) with K Basin fuel transported to the CVDF. The MCOs will be processed at the CVDF to remove free water from the fuel cells (packages). Following processing at the CVDF, the MCOs will be transported to the CSB for interim storage until a long-term storage solution can be implemented. This operation is expected to start in November 2000. A Fire Hazard Analysis (FHA) is required for all new facilities and all nonreactor nuclear facilities, in accordance with U.S. Department of Energy (DOE) Order 5480.7A, Fire Protection. This FHA has been prepared in accordance with DOE 5480.7A and HNF-PRO-350, Fire Hazard Analysis Requirements. Additionally, requirements or criteria contained in DOE, Richland Operations Office (RL) RL Implementing Directive (RLID) 5480.7, Fire Protection, or other DOE documentation are cite...

  6. Sodium Fire Demonstration Facility Design and Operation

    International Nuclear Information System (INIS)

    Cho, Youngil; Kim, Jong-Man; Lee, Jewhan; Hong, Jonggan; Yeom, Sujin; Cho, Chungho; Jung, Min-Hwan; Gam, Da-Young; Jeong, Ji-Young

    2014-01-01

    Although sodium has good characteristics such as high heat transfer rate and stable nuclear property, it is difficult to manage because of high reactivity. Sodium is solid at the room temperature and it easily reacts with oxygen resulting in fire due to the reaction heat. Thus, sodium must be stored in a chemically stable place, i.e., an inert gas-sealed or oil filled vessel. When a sodium fire occurs, the Na 2 O of white fume is formed. It is mainly composed of Na 2 O 2 , NaOH, and Na 2 CO 3 , ranging from 0.1 to several tens of micrometers in size. It is known that the particle size increases by aggregation during floating in air. Thus, the protection method is important and should be considered in the design and operation of a sodium system. In this paper, sodium fire characteristics are described, and the demonstration utility of outbreak of sodium fire and its extinguishing is introduced. In this paper, sodium fire characteristics and a demonstration facility are described. The introduced sodium fire demonstration facility is the only training device used to observe a sodium fire and extinguish it domestically. Furthermore, the type of sodium fire will be diversified with the enhancement of the utility. It is expected that this utility will contribute to experience in the safe treatment of sodium by the handlers

  7. Design requirements document for Exploratory Shaft Facility site preparation and selected facilities

    International Nuclear Information System (INIS)

    Valentich, D.J.

    1987-01-01

    This document describes design requirements for portions of the Exploratory Shaft Facility site preparation work, shop and warehouse facility, change house, and support facilities. The information presented herein defines constraints, performance criteria, functional requirements, and definitions for the site preparation and facility related work. 1 fig

  8. Moderator Demonstration Facility Design and Optimization

    Energy Technology Data Exchange (ETDEWEB)

    McClanahan, Tucker C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gallmeier, Franz X. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Iverson, Erik B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-02-01

    The Spallation Neutron Source (SNS) facility at Oak Ridge National Laboratory (ORNL) is implementing a Moderator Demonstration Facility (MDF) to demonstrate the performance characteristics of advanced moderators central to the Second Target Station (STS) for SNS. The MDF will use the "spare" front-end installation within the SNS accelerator support complex – an ion source, radio-frequency quadrupole (RFQ) accelerator, and medium-energy beam transport (MEBT) chopper - to provide a 2.5 MeV proton beam of peak current 50 mA and maximum pulse length of less than 10 s at a repetition rate of no more than 60 Hz to a suitable neutron-producing target to demonstrate those aspects of moderator performance necessary to meet the goals of the STS design e ort. The accelerator beam parameters are not open to variation beyond that described above - they are fixed by the nature of the spare front-end installation (the Integrated Test Stand Facility; ITSF). Accordingly, there are some neutronic challenges in developing prototypic moderator illumination from a very non-prototypic primary neutron source; the spallation source we are attempting to mimic has an extended neutron source volume approximately 40 cm long (in the direction of the proton beam), approximately 10 cm wide (horizontally transverse to the proton beam) and approximately 5 cm high (vertically transverse to the proton beam), and an isotropic evaporation energy spectrum with mean energy above 1 MeV. In contrast, the primary neutron source available from the 7Li(p,n) reaction (the most prolific at 2.5 MeV proton energy by more than an order of magnitude) is strongly anisotropic, with an energy spectrum that is both strongly dependent on emission angle and kinematically limited to less than 700 keV, and the interaction zone between the incident protons and any target material (neutron-producing or not) is intrinsically limited to a few tens of microns. The MDF will be unique and innovative amongst the world

  9. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

    Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

    2010-07-01

    The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

  10. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    The Basis for Design established the functional requirements and design criteria for an Integral Monitored Retrievable Storage (MRS) facility. The MRS Facility design, described in this report, is based on those requirements and includes all infrastructure, facilities, and equipment required to routinely receive, unload, prepare for storage, and store spent fuel (SF), high-level waste (HLW), and transuranic waste (TRU), and to decontaminate and return shipping casks received by both rail and truck. The facility is complete with all supporting facilities to make the MRS Facility a self-sufficient installation

  11. Large coil test facility conceptual design report

    International Nuclear Information System (INIS)

    Nelms, L.W.; Thompson, P.B.; Mann, T.L.

    1978-02-01

    In the development of a superconducting toroidal field (TF) magnet for The Next Step (TNS) tokamak reactor, several different TF coils, about half TNS size, will be built and tested to permit selection of a design and fabrication procedure for full-scale TNS coils. A conceptual design has been completed for a facility to test D-shaped TF coils, 2.5 x 3.5-m bore, operating at 4-6 K, cooled either by boiling helium or by forced-flow supercritical helium. Up to six coils can be accommodated in a toroidal array housed in a single vacuum tank. The principal components and systems in the facility are an 11-m vacuum tank, a test stand providing structural support and service connections for the coils, a liquid nitrogen system, a system providing helium both as saturated liquid and at supercritical pressure, coils to produce a pulsed vertical field at any selected test coil position, coil power supplies, process instrumentation and control, coil diagnostics, and a data acquisition and handling system. The test stand structure is composed of a central bucking post, a base structure, and two horizontal torque rings. The coils are bolted to the bucking post, which transmits all gravity loads to the base structure. The torque ring structure, consisting of beams between adjacent coils, acts with the bucking structure to react all the magnetic loads that occur when the coils are energized. Liquid helium is used to cool the test stand structure to 5 K to minimize heat conduction to the coils. Liquid nitrogen is used to precool gaseous helium during system cooldown and to provide thermal radiation shielding

  12. Yucca Mountain Project Subsurface Facilities Design

    International Nuclear Information System (INIS)

    Linden, A.; Saunders, R.S.; Boutin, R.J.; Harrington, P.G.; Lachman, K.D.; Trautner, L.J.

    2002-01-01

    Four units of the Topopah Springs formation (volcanic tuff) are considered for the proposed repository: the upper lithophysal, the middle non-lithophysal, the lower lithophysal, and the lower non-lithophysal. Yucca Mountain was recently designated the site for a proposed repository to dispose of spent nuclear fuel and high-level radioactive waste. Work is proceeding to advance the design of subsurface facilities to accommodate emplacing waste packages in the proposed repository. This paper summarized recent progress in the design of subsurface layout of the proposed repository. The original Site Recommendation (SR) concept for the subsurface design located the repository largely within the lower lithophysal zone (approximately 73%) of the Topopah The Site Recommendation characterized area suitable for emplacement consisted of the primary upper block, the lower block and the southern upper block extension. The primary upper block accommodated the mandated 70,000 metric tons of heavy metal (MTHM) at a 1.45 kW/m hear heat load. Based on further study of the Site Recommendation concept, the proposed repository siting area footprint was modified to make maximum use of available site characterization data, and thus, reduce uncertainties associated with performance assessment. As a result of this study, a modified repository footprint has been proposed and is presently being review for acceptance by the DOE. A panel design concept was developed to reduce overall costs and reduce the overall emplacement schedule. This concept provides flexibility to adjust the proposed repository subsurface layout with time, as it makes it unnecessary to ''commit'' to development of a large single panel at the earliest stages of construction. A description of the underground layout configuration and influencing factors that affect the layout configuration are discussed in the report

  13. Design, Evaluation and Test Technology Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The mission of this facility, which is composed of numerous specialized facilities, is to provide capabilities to simulate a wide range of environments for component...

  14. Space power distribution system technology. Volume 3: Test facility design

    Science.gov (United States)

    Decker, D. K.; Cannady, M. D.; Cassinelli, J. E.; Farber, B. F.; Lurie, C.; Fleck, G. W.; Lepisto, J. W.; Messner, A.; Ritterman, P. F.

    1983-01-01

    The AMPS test facility is a major tool in the attainment of more economical space power. The ultimate goals of the test facility, its primary functional requirements and conceptual design, and the major equipment it contains are discussed.

  15. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 5 Book 1, contains cost estimate summaries for a monitored retrievable storage (MRS) facility. The cost estimate is based on the engineering performed during the conceptual design phase of the MRS Facility project

  16. Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

    International Nuclear Information System (INIS)

    Shank, D.R.

    1995-01-01

    The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium

  17. Learning Design at White Sands Test Facility

    Science.gov (United States)

    Grotewiel, Shane

    2010-01-01

    During the Fall of 2010, I spent my time at NASA White Sands Test Facility in Las Cruces, NM as an Undergraduate Student Research Program (USRP) Intern. During that time, I was given three projects to work on: Large Altitude Simulation System (LASS) basket strainer, log books, and the design of a case for touch screen monitors used for simulations. I spent most of my time on the LASS basket strainer. The LASS system has a water feed line with a basket strainer that filters out rust. In 2009, there were three misfires which cost approximately $27,000 and about 8% of the allotted time. The strainer was getting a large change in pressure that would result in a shutdown of the system. I have designed a new basket that will eliminate the large pressure change and it can be used with the old basket strainer housing. The LASS system has three steam generators (modules). Documents pertaining to these modules are stored electronically, and the majority of the documents are not able to be searched with keywords, so they have to be gone through one by one. I have come up with an idea on how to organize these files so that the Propulsion Department may efficiently search through the documents needed. Propulsion also has a LASS simulator that incorporates two touch screen monitors. Currently these monitors are in six foot by two foot metal cabinet on wheels. During simulation these monitors are used in the block house and need to be taken out of the block house when not in use. I have designed different options for hand held cases for storing and transporting the monitors in and out of the block house. The three projects previously mentioned demonstrate my contributions to the Propulsion Department and have taught me real world experience that is essential in becoming a productive engineer.

  18. Design of 131I in patient facilities

    International Nuclear Information System (INIS)

    Towson, J.; Collins, L.; Smart, R.; Walker, B.; Westmead Hospital, Westmead, NSW; St George Hospital, Sydney, NSW; Prince of Wales Hospital, Sydney, NSW

    1999-01-01

    Full text: A Design Guideline for 131 I Therapy Facilities (1996) has been developed for the NSW Hospital and University Radiation Safety Officers Group (HURSOG) with recommendations on isolation rooms and delay tanks for storing waste water from the patient toilets. Shielding design for an isolation room is based on a methodology widely used in radiology and radiotherapy. The transmission factor (K) to achieve a dose limit of 20 μSv per week beyond a barrier is calculated for a specified number of 131 I patients per week, average administered activity, and distance (source to recipient on further side of barrier). Default values are recommended for the workload, 131 I dose rate and occupancy factors in the surrounding areas if not known. From the calculated value of K, the barrier thickness in lead or masonry can be obtained from tabulated attenuation data. Delay tanks are designed as a pair, alternately filling and holding waste water until the 131 I activity discharged to the sewer complies with a limit of 20 ALI (i.e. 18 MBq) per week recommended by the National Health and Medical Research Council and acceptable to local water authorities. The Guideline has been used to design shielding for two isolation beds which were relocated to a ward with plasterboard walls. The two nearest adjacent beds were at a distance of 3.5 m. Due to space constraints, lead panels up to 25 mm thick were used for shielding rather than 30 cm thick concrete walls. A 14-week radiation survey of surrounding areas with TLD dosimeters during treatment of 33 patients per room, with an average administered activity of 5.1 GBq, showed doses at the four adjacent beds were below the design limit of 80 μSv per week for an occupancy factor of 0.25 conservatively based on length-of-stay bed data for the ward. Delay tanks installed at another hospital and sized according to the Guideline at 7 m 3 per bed fill to 70-80% of capacity during a 3-month fill/3-month decay cycle

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

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

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  1. Modern tornado design of nuclear and other potentially hazardous facilities

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Zhao, Y.

    1996-01-01

    Tornado wind loads and other tornado phenomena, including tornado missiles and differential pressure effects, have not usually been considered in the design of conventional industrial, commercial, or residential facilities in the United States; however, tornado resistance has often become a design requirement for certain hazardous facilities, such as large nuclear power plants and nuclear materials and waste storage facilities, as well as large liquefied natural gas storage facilities. This article provides a review of current procedures for the design of hazardous industrial facilities to resist tornado effects. 23 refs., 19 figs., 13 tabs

  2. Waste Encapsulation and Storage Facility (WESF) Design Reconstitution Plan

    International Nuclear Information System (INIS)

    HERNANDEZ, R.

    1999-01-01

    The purpose of Design Reconstitution is to establish a Design Baseline appropriate to the current facility mission. The scope of this plan is to ensure that Systems, Structures and Components (SSC) identified in the WESF Basis for Interim Operation (HNF-SDWM-BIO-002) are adequately described and documented, in order to support facility operations. In addition the plan addresses the adequacy of selected Design Topics which are also crucial for support of the facility Basis for Interim Operation (BIO)

  3. 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

  4. Exergoeconomic optimization of an ammonia-water hybrid heat pump for heat supply in a spray drying facility

    DEFF Research Database (Denmark)

    Jensen, Jonas Kjær; Markussen, Wiebke Brix; Reinholdt, Lars

    2014-01-01

    Spray drying facilities are among the most energy intensive industrial processes. Using a heat pump to recover waste heat and replace gas combustion has the potential to attain both economic and emissions savings. In the case examined a drying gas of ambient air is heated to 200 XC. The inlet flow...

  5. Design and commissioning experience of SALT facility

    Science.gov (United States)

    De Kock, Mariana; Venter, Sarel

    2004-09-01

    The commissioning experience of the facility for SALT is compared to the results of the analysis done during the design. A false steel floor incorporating forced ventilation that extends around the telescope azimuth pier is installed to prevent heat radiating from the concrete surfaces on nights when the ambient temperature drops to below room temperature. An infrared scan was done on this floor to verify that no heat is radiated into the telescope chamber from either the concrete or the warmer rooms underneath. The SALT site is windy all year round, and in order to utilize this natural resource and get better ventilation, adjustable louvers are used for natural ventilation. The control system automatically adjusts the louver openings depending on the wind speed and relative direction of the dome opening to achieve enough air changes during wind still nights. The louvers are throttled to limit windshake on the structure on windy nights. Results of the computational fluid dynamic analysis (CFD) and actual measurements are presented showing adequate temperature distribution at low wind speeds. The correlation between the CFD and actual measurements are discussed, with reference to the surface and air temperatures in the telescope chamber under different ambient conditions. The telescope chamber and dome are built out of insulation panels to limit energy losses during the day when the chamber is air conditioned. It also ensures thermal inertia of the building is low and consequently allows its temperature to react quickly to changes in external ambient temperature. The correlation between the expected and actual capacity of the air conditioners are also discussed.

  6. Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

    1999-06-01

    A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours.

  7. Construction of irradiated material examination facility-basic design

    International Nuclear Information System (INIS)

    Ro, Seung Gy; Kim, Eun Ka; Hong, Gye Won; Herr, Young Hoi; Hong, Kwon Pyo; Lee, Myeong Han; Baik, Sang Youl; Choo, Yong Sun; Baik, Seung Je

    1989-02-01

    The basic design of the hot cell facility which has the main purpose of doing mechanical and physical property tests of irradiated materials, the examination process, and the annexed facility has been made. Also basic and detall designs for the underground excavation work have been performed. The project management and tasks required for the license application have been carried out in due course. The facility is expected to be completed by the end of 1992, if the budgetary support is sufficient. (Author)

  8. Effects of temperature on concrete cask in a dry storage facility for spent nuclear fuels

    International Nuclear Information System (INIS)

    Huang Weiqing; Wu Ruixian; Zheng Yukuan

    2011-01-01

    In the dry storage of spent nuclear fuels,concrete cask serves both as a shielding and a structural containment. The concrete in the storage facility is expected to endure the decay heat of the spent nuclear fuel during its service life. Thus, effects of the sustaining high temperature on concrete material need be evaluated for safety of the dry storage facility. In this paper, we report an experimental program aimed at investigating possible high temperature effects on properties of concrete, with emphasis on the mechanical stability, porosity,and crack-resisting ability of concrete mixes prepared using various amounts of Portland cement, fly ash, and blast furnace slag. The experimental results obtained from concrete specimens exposed to a temperature of 94 degree C for 90 days indicate that: (1) compressive strength of the concrete remains practically unchanged; (2) the ultrasonic pulse velocity, and dynamic modulus of elasticity of the concrete decrease in early stage of the high-temperature exposure,and gradually become stable with continuing exposure; (3) shrinkage of concrete mixes exhibits an increase in early stage of the exposure and does not decrease further with time; (4) concrete mixes containing pozzolanic materials,including fly ash and blast furnace slag, show better temperature-resisting characteristics than those using only Portland cement. (authors)

  9. MEMS/Electronic Device Design and Characterization Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility allows DoD to design and characterize state-of-the-art microelectromechanical systems (MEMS) and electronic devices. Device designers develop their own...

  10. Design handbook : energy efficiency and water conservation in NAS facilities

    Science.gov (United States)

    1997-09-30

    This handbook was created to provide definitive energy efficiency and water conservation design criteria for the design of NAS facilities. FAA-HDBK-001 provides implementation strategies and tools to comply with E.O. 12902, Energy and Water Conservat...

  11. Design Guide for Category I reactors critical facilities

    International Nuclear Information System (INIS)

    Brynda, W.J.; Powell, R.W.

    1978-08-01

    The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned critical facilities be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission

  12. Accelerator-driven subcritical facility:Conceptual design development

    Science.gov (United States)

    Gohar, Yousry; Bolshinsky, Igor; Naberezhnev, Dmitry; Duo, Jose; Belch, Henry; Bailey, James

    2006-06-01

    A conceptual design development of an accelerator-driven subcritical facility has been carried out in the preparation of a joint activity with Kharkov Institute of Physics and Technology of Ukraine. The main functions of the facility are the medical isotope production and the support of the Ukraine nuclear industry. An electron accelerator is considered to drive the subcritical assembly. The neutron source intensity and spectrum have been studied. The energy deposition, spatial neutron generation, neutron utilization fraction, and target dimensions have been quantified to define the main target performance parameters, and to select the target material and beam parameters. Different target conceptual designs have been developed based the engineering requirements including heat transfer, thermal hydraulics, structure, and material issues. The subcritical assembly is designed to obtain the highest possible neutron flux level with a Keff of 0.98. Different fuel materials, uranium enrichments, and reflector materials are considered in the design process. The possibility of using low enrichment uranium without penalizing the facility performance is carefully evaluated. The mechanical design of the facility has been developed to maximize its utility and minimize the time for replacing the target and the fuel assemblies. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements, upgrades, and new missions. In addition, it has large design margins to accommodate different operating conditions and parameters. In this paper, the conceptual design and the design analyses of the facility will be presented.

  13. Design, Construction and Evaluation of a Dry Solar Sterilizer

    International Nuclear Information System (INIS)

    Hernández Fereira, Arcelio A.

    2017-01-01

    The objective of the work was the search of an alternative for sterilization using solar energy. For such purposes, a dry solar sterilizer of 4276 cm3 capacity was designed, constructed and evaluated. Potential users would be rural medical posts in areas without electricity, health posts in military units under field conditions, and experimental microbiology stations. The evaluation included the determination of the energy efficiency of the sterilizer, the economic evaluation against other variants and the biological safety assessment. The developed equipment reached the sterilization temperature for levels of the direct component of the solar radiation higher than 300 W/m2 in 14 minutes, corresponding to an average heating rate of 13 0C/minute, higher than that of an electric furnace. Its energy efficiency with direct solar radiation of 310.5 W/m2 was 53.79%. The equipment is of easy construction, simple operation and very low cost. (author)

  14. Performance and design requirements for a graphics display research facility

    International Nuclear Information System (INIS)

    Tillitt, D.N.; Petersen, R.J.; Smith, R.L.

    1982-06-01

    Performance and design requirements for a Graphics Display Research Facility (GDRF) are presented. The GDRF is an evolutionary, computer-based, human-engineering experimentation center that is specifically designed to address long-term research issues associated with automation, human performance, and risk in the operation of nuclear facilities. Research capabilities provided by this facility will directly support the licensing and regulation of nuclear facilities within the United States. Research provided by this facility is intended to satisfy the Nuclear Regulatory Commission's (NRC) needs to: (a) confirm design adequacy of, and develop evaluation criteria for, computerized graphic displays and other information presentation mechanisms proposed for use in nuclear power plants, and (b) assess the possible effects on operator performance of computer-based operator-support concepts. The ultimate goal of this research is to support regulatory directives for minimizing the risk of human error in the operation of nuclear facilities

  15. Monitored Retrievable Storage conceptual system study: dry receiving and handling facility

    International Nuclear Information System (INIS)

    1984-01-01

    A preconceptual design and estimate for a MRS receiving and handling (R and H) facility at a hypothetical site in the United States are presented. The facility consists of a receiving and handling building plus associated operating buildings, system, and site development features. The R and H building and the supporting buildings and site development features are referred to as the R and H area. Adjoining the R and H area will be an interim waste storage area currently being considered by others. The desirability of building a full capacity (3000-MTU) MRS facility initially versus adding additional capacity at a later date in a phased construction program was investigated. Several advantages of phased construction include incorporation of new designs, modification of receiving-handling-packaging, and changes in regulatory requirements or the waste management program which may develop following startup and operation of an 1800-MTU MRS facility. The cost of a 3000-MTU MRS facility constructed initially was estimated at $193,200,000. If a phased construction program was implemented, including escalation to the mid-point of Phase 2 construction, a capital expenditure of $215,300,000 is estimated - a cost penalty of $22,100,000 or about 11% for phased construction

  16. Design of GMP compliance radiopharmaceutical production facility in MINT

    International Nuclear Information System (INIS)

    Anwar Abd Rahman; Shaharum Ramli; M Rizal Mamat Ibrahim; Rosli Darmawan; Yusof Azuddin Ali; Jusnan Hashim

    2005-01-01

    In 1985, MINT built the only radiopharmaceutical production facility in Malaysia. The facility was designed based on IAEA (International Atomic Energy Agency) standard guidelines which provide radiation safety to the staff and the surrounding environment from radioactive contamination. Since 1999, BPFK (Biro Pengawalan Farmaseutikal Kebangsaan) has used the guidelines from Pharmaceutical Inspection Convention Scheme (PICS) to meet the requirements of the Good Manufacturing Practice (GMP) for Pharmaceutical Products. In the guidelines, the pharmaceutical production facility shall be designed based on clean room environment. In order to design a radiopharmaceutical production facility, it is important to combine the concept of radiation safety and clean room to ensure that both requirements from GMP and IAEA are met. The design requirement is necessary to set up a complete radiopharmaceutical production facility, which is safe, has high production quality and complies with the Malaysian and International standards. (Author)

  17. A Dynamic Design Space for Primary Drying During Batch Freeze-Drying

    DEFF Research Database (Denmark)

    Mortier, Séverine Thérèse F C; Van Bockstal, Pieter Jan; Nopens, Ingmar

    2016-01-01

    Biopharmaceutical products are emerging within the pharmaceutical industry. However, biopharmaceuticals are often unstable in aqueous solution. Freeze-drying (lyophilisation) is the preferred method to achieve a stable product with an increased shelf-life. During batch freeze-drying, there are only...

  18. A case study of collaborative facilities use in engineering design

    Energy Technology Data Exchange (ETDEWEB)

    Monroe, Laura M [Los Alamos National Laboratory

    2009-01-01

    In this paper we describe the use of visualization tools and facilities in the collaborative design of a replacement weapons system, the Reliable Replacement Warhead. We used not only standard collaboration methods but also a range of visualization software and facilities to bring together domain specialists from laboratories across the country to collaborate on the design and integrate this disparate input early in the design.

  19. Integral Monitored Retrievable Storage (MRS) Facility conceptual basis for design

    International Nuclear Information System (INIS)

    1985-10-01

    The purpose of the Conceptual Basis for Design is to provide a control document that establishes the basis for executing the conceptual design of the Integral Monitored Retrievable Storage (MRS) Facility. This conceptual design shall provide the basis for preparation of a proposal to Congress by the Department of Energy (DOE) for construction of one or more MRS Facilities for storage of spent nuclear fuel, high-level radioactive waste, and transuranic (TRU) waste. 4 figs., 25 tabs

  20. Hanford Site waste tank farm facilities design reconstitution program plan

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1994-01-01

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

  1. Cold Vacuum Drying Safety Class Instrumentation and Control System Design Description SYS 93-2

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) Safety Class Instrumentation and Control system (SCIC). The SCIC provides safety functions and features to protect the environment, off-site and on-site personnel and equipment. The function of the SCIC is to provide automatic trip features, valve interlocks, alarms, indication and control for the cold vacuum drying process

  2. Interim dry cask storage of irradiated Fast Flux Test Facility fuel

    International Nuclear Information System (INIS)

    Scott, P.L.

    1994-09-01

    The Fast Flux Test Facility (FFTF), located at the US Department of Energy's (DOE'S) Hanford Site, is the largest, most modern, liquid metal-cooled test reactor in the world. This paper will give an overview of the FFTF Spent Fuel Off load project. Major discussion areas will address the status of the fuel off load project, including an overview of the fuel off load system and detailed discussion on the individual components that make up the dry cask storage portion of this system. These components consist of the Interim Storage Cask (ISC) and Core Component Container (CCC). This paper will also discuss the challenges that have been addressed in the evolution of this project

  3. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 6 Book 1, contains information on design studies of a Monitored Retrievable Storage (MRS) facility. Topics include materials handling; processing; support systems; support utilities; spent fuel; high-level waste and alpha-bearing waste storage facilities; and field drywell storage

  4. Anatomy Education in Namibia: Balancing Facility Design and Curriculum Development

    Science.gov (United States)

    Wessels, Quenton; Vorster, Willie; Jacobson, Christian

    2012-01-01

    The anatomy curriculum at Namibia's first, and currently only, medical school is clinically oriented, outcome-based, and includes all of the components of modern anatomical sciences i.e., histology, embryology, neuroanatomy, gross, and clinical anatomy. The design of the facilities and the equipment incorporated into these facilities were directed…

  5. Design and operations at the National Tritium Labelling Facility

    International Nuclear Information System (INIS)

    Morimoto, H.; Williams, P.G.

    1991-09-01

    The National Tritium Labelling Facility (NTLF) is a multipurpose facility engaged in tritium labeling research. It offers to the biomedical research community a fully equipped laboratory for the synthesis and analysis of tritium labeled compounds. The design of the tritiation system, its operations and some labeling techniques are presented

  6. A case study of collaborative facilities in engineering design

    Energy Technology Data Exchange (ETDEWEB)

    Monroe, Laura M [Los Alamos National Laboratory; Pugmire, David [ORNL

    2008-01-01

    In this paper we describe the use of visualization tools and facilities in the collaborative design of a replacement weapons system, the Reliable Replacement Warhead (RRW). We used not only standard collaboration methods but also a range of visualization software and facilities to bring together domain specialists from laboratories across the country to collaborate on the design and integrate this disparate input early in the design. This was the first time in U.S. weapons history that a weapon had been designed in this collaborative manner. Benefits included projected cost savings, design improvements and increased understanding across the project.

  7. Overview of High Power Vacuum Dry RF Load Designs

    Energy Technology Data Exchange (ETDEWEB)

    Krasnykh, Anatoly [SLAC National Accelerator Lab., Menlo Park, CA (United States)

    2015-08-27

    A specific feature of RF linacs based on the pulsed traveling wave (TW) mode of operation is that only a portion of the RF energy is used for the beam acceleration. The residual RF energy has to be terminated into an RF load. Higher accelerating gradients require higher RF sources and RF loads, which can stably terminate the residual RF power. RF feeders (from the RF source though the accelerating section to the load) are vacuumed to transmit multi-megawatt high power RF. This overview will outline vacuumed RF loads only. A common method to terminate multi-MW RF power is to use circulated water (or other liquid) as an absorbing medium. A solid dielectric interface (a high quality ceramic) is required to separate vacuum and liquid RF absorber mediums. Using such RF load approaches in TW linacs is troubling because there is a fragile ceramic window barrier and a failure could become catastrophic for linac vacuum and RF systems. Traditional loads comprising of a ceramic disk have limited peak and average power handling capability and are therefore not suitable for high gradient TW linacs. This overview will focus on ''vacuum dry'' or ''all-metal'' loads that do not employ any dielectric interface between vacuum and absorber. The first prototype is an original design of RF loads for the Stanford Two-Mile Accelerator.

  8. 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.

  9. A Facilities Manager's Guide to Green Building Design.

    Science.gov (United States)

    Simpson, Walter

    2001-01-01

    Explains how the "green building" approach to educational facilities design creates healthy, naturally lit, attractive buildings with lower operating and life cycle costs. Tips on getting started on a green design and overcoming the barriers to the green design concept are discussed. (GR)

  10. Design and construction of the Fuels and Materials Examination Facility

    International Nuclear Information System (INIS)

    Burgess, C.A.

    1979-01-01

    Final design is more than 85 percent complete on the Fuels and Materials Examination Facility, the facility for post-irradiation examination of the fuels and materials tests irradiated in the FFTF and for fuel process development, experimental test pin fabrication and supporting storage, assay, and analytical chemistry functions. The overall facility is generally described with specific information given on some of the design features. Construction has been initiated and more than 10% of the construction contracts have been awarded on a fixed price basis

  11. 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

  12. 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

  13. Partial gravity - Human impacts on facility design

    Science.gov (United States)

    Capps, Stephen; Moore, Nathan

    1990-01-01

    Partial gravity affects the body differently than earth gravity and microgravity environments. The main difference from earth gravity is human locomotion; while the main dfference from microgravity is the specific updown orientation and reach envelopes which increase volume requirements. Much data are available on earth gravity and microgravity design; however, very little information is available on human reactions to reduced gravity levels in IVA situations (without pressure suits). Therefore, if humans commit to permanent lunar habitation, much research should be conducted in the area of partial gravity effects on habitat design.

  14. Conceptual capital-cost estimate and facility design of the Mirror-Fusion Technology Demonstration Facility

    International Nuclear Information System (INIS)

    1982-09-01

    This report contains contributions by Bechtel Group, Inc. to Lawrence Livermore National Laboratory (LLNL) for the final report on the conceptual design of the Mirror Fusion Technology Demonstration Facility (TDF). Included in this report are the following contributions: (1) conceptual capital cost estimate, (2) structural design, and (3) plot plan and plant arrangement drawings. The conceptual capital cost estimate is prepared in a format suitable for inclusion as a section in the TDF final report. The structural design and drawings are prepared as partial inputs to the TDF final report section on facilities design, which is being prepared by the FEDC

  15. ESO Catalogue Facility Design and Performance

    Science.gov (United States)

    Moins, C.; Retzlaff, J.; Arnaboldi, M.; Zampieri, S.; Delmotte, N.; Forchí, V.; Klein Gebbinck, M.; Lockhart, J.; Micol, A.; Vera Sequeiros, I.; Bierwirth, T.; Peron, M.; Romaniello, M.; Suchar, D.

    2013-10-01

    The ESO Phase 3 Catalogue Facility provides investigators with the possibility to ingest catalogues resulting from ESO public surveys and large programs and to query and download their content according to positional and non-positional criteria. It relies on a chain of tools that covers the complete workflow from submission to validation and ingestion into the ESO archive and catalogue repository and a web application to browse and query catalogues. This repository consists of two components. One is a Sybase ASE relational database where catalogue meta-data are stored. The second one is a Sybase IQ data warehouse where the content of each catalogue is ingested in a specific table that returns all records matching a user's query. Spatial indexing has been implemented in Sybase IQ to speed up positional queries and relies on the Spherical Geometry Toolkit from the Johns Hopkins University which implements the Hierarchical Triangular Mesh (HTM) algorithm. It is based on a recursive decomposition of the celestial sphere in spherical triangles and the assignment of an index to each of them. It has been complemented with the use of optimized indexes on the non-positional columns that are likely to be frequently used as query constraints. First tests performed on catalogues such as 2MASS have confirmed that this approach provides a very good level of performance and a smooth user experience that are likely to facilitate the scientific exploitation of catalogues.

  16. Biomedical computing facility interface design plan

    Science.gov (United States)

    Puckett, R. D.

    1971-01-01

    The results are presented of a design study performed to establish overall system interface requirements for the Biomedical Laboratories Division's Sigma-3 computer system. Emphasis has been placed upon the definition of an overall implementation plan and associated schedule to meet both near-term and long-range requirements within the constraints at available resources.

  17. SNL/CA Facilities Management Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Rabb, David [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Clark, Eva [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2014-12-01

    At Sandia National Laboratories in California (SNL/CA), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/CA applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule.

  18. Preconceptual design for a Monitored Retrievable Storage (MRS) transfer facility

    International Nuclear Information System (INIS)

    Woods, W.D.; Jowdy, A.K.; Smith, R.I.

    1990-09-01

    The contract between the DOE and the utilities specifies that the DOE will receive spent fuel from the nuclear utilities in 1998. This study investigates the feasibility of employing a simple Transfer Facility which can be constructed quickly, and operate while the full-scale MRS facilities are being constructed. The Transfer Facility is a hot cell designed only for the purpose of transferring spent fuel assemblies from the Office of Civilian Radioactive Waste Management (OCRWM) transport casks (shipped from the utility sites) into onsite concrete storage casks. No operational functions other than spent fuel assembly transfers and the associated cask handling, opening, and closing would be performed in this facility. Radioactive waste collected in the Transfer Facility during operations would be stored until the treatment facilities in the full-scale MRS facility became operational, approximately 2 years after the Transfer Facility started operation. An alternate wherein the Transfer Facility was the only waste handling building on the MRS site was also examined and evaluated. 6 figs., 26 tabs

  19. Structural design considerations for a radwaste processing facility

    International Nuclear Information System (INIS)

    Foelber, S.C.; Sabbe, M.A.

    1985-01-01

    The structural engineer needs to consider several criteria when designing a radioactive-waste processing facility in order to properly balance the requirements of safety and economy. This paper addresses the design criteria and structural design of a vitrification building and the special equipment and supports associated with remote process operations. In addition, approaches to construction, and the role of scale models to aid in engineering design and construction are discussed. 5 figures

  20. Power supply design for Hadron Facility

    International Nuclear Information System (INIS)

    Karady, G.; Kansog, J.; Thiessen, H.A.; Schneider, E.

    1987-01-01

    Recently, a study investigated the feasibility of building a large 60 GeV, kaon factory accelerator. This paper presents the conceptual design of the magnet power supplies and energy storage system. In this study the following three systems were investigated: (a) power supply using storage generator; (b) power supply using inductive storage device; and (c) resonant power supplies. These systems were analyzed from both technical and economical points of view. It was found that all three systems are feasible and can be built using commercially available components. From a technical point of view, the system using inductive storage is the most advantageous. The resonant power supply is the most economical solution

  1. 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)

  2. 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).

  3. CIF---Design basis for an integrated incineration facility

    International Nuclear Information System (INIS)

    Bennett, G.F.

    1991-01-01

    This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

  4. Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

    International Nuclear Information System (INIS)

    1975-12-01

    The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

  5. Conceptual design report for Central Waste Disposal Facility

    International Nuclear Information System (INIS)

    1984-01-01

    The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables

  6. The Mixed Waste Management Facility. Preliminary design review

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

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

  7. The Mixed Waste Management Facility. Preliminary design review

    International Nuclear Information System (INIS)

    1995-01-01

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

  8. Radioactive material dry-storage facility and radioactive material containing method

    International Nuclear Information System (INIS)

    Kanai, Hidetoshi; Kumagaya, Naomi; Ganda, Takao.

    1997-01-01

    The present invention provides a radioactive material dry storage facility which can unify the cooling efficiency of a containing tube and lower the pressure loss in a storage chamber. Namely, a cylindrical body surrounds a first containing tube situated on the side of an air discharge portion among a plurality of containing tubes and forms an annular channel extending axially between the cylindrical body and the first containing tube. An air flow channel partitioning member is disposed below a second containing tube situated closer to an air charging portion than the first containing tube. A first air flow channel is formed below the air channel partitioning member extending from the air charging portion to the annular channel. The second air channel is formed above the air channel partitioning member and extends from the air charging portion to the air discharge portion by way of a portion between the second containing tubes and the portion between the cylindrical body and the first containing tube. Then, low temperature air can be led from the air charging portion to the periphery of the first containing tube. The effect of cooling the first containing tube can be enhanced. The difference between the cooling efficiency between the second containing tube and the first containing tube is decreased. (I.S.)

  9. Threats, design limits and design windows for laser IFE dry wall chambers

    International Nuclear Information System (INIS)

    Raffray, A. Rene

    2005-01-01

    The High Average Power Laser (HAPL) program is carrying out a coordinated effort to develop inertial fusion energy based on lasers, direct-drive targets and a dry wall chamber. The dry wall must accommodate the ion and photon threat spectra from the fusion micro-explosion over its required lifetime. This paper summarizes the current HAPL strategy on the armor/first wall configuration based on tungsten and ferritic steel as preferred armor and structural materials, respectively. The thermal performance of an example fully dense tungsten armor configuration on a ferritic steel first wall is described showing the basis for separating the high energy accommodation function of the armor from the structural function of the first wall. Example design operating windows for the armor, first wall and blanket are presented based on different requirements and constraints. The possibility of utilizing an engineered porous armor is discussed. Key chamber wall and armor issues are summarized

  10. Threats, design limits and design windows for laser IFE dry wall chambers

    Science.gov (United States)

    Raffray, A. René; HAPL Team

    2005-12-01

    The High Average Power Laser (HAPL) program is carrying out a coordinated effort to develop inertial fusion energy based on lasers, direct-drive targets and a dry wall chamber. The dry wall must accommodate the ion and photon threat spectra from the fusion micro-explosion over its required lifetime. This paper summarizes the current HAPL strategy on the armor/first wall configuration based on tungsten and ferritic steel as preferred armor and structural materials, respectively. The thermal performance of an example fully dense tungsten armor configuration on a ferritic steel first wall is described showing the basis for separating the high energy accommodation function of the armor from the structural function of the first wall. Example design operating windows for the armor, first wall and blanket are presented based on different requirements and constraints. The possibility of utilizing an engineered porous armor is discussed. Key chamber wall and armor issues are summarized.

  11. Select Generic Dry-Storage Pilot Plant Design for Safeguards and Security by Design (SSBD) per Used Fuel Campaign

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-05-26

    As preparation to the year-end deliverable (Provide SSBD Best Practices for Generic Dry-Storage Pilot Scale Plant) for the Work Package (FT-15LA040501–Safeguards and Security by Design for Extended Dry Storage), the initial step was to select a generic dry-storage pilot plant design for SSBD. To be consistent with other DOE-NE Fuel Cycle Research and Development (FCR&D) activities, the Used Fuel Campaign was engaged for the selection of a design for this deliverable. For the work Package FT-15LA040501–“Safeguards and Security by Design for Extended Dry Storage”, SSBD will be initiated for the Generic Dry-Storage Pilot Scale Plant described by the layout of Reference 2. SSBD will consider aspects of the design that are impacted by domestic material control and accounting (MC&A), domestic security, and international safeguards.

  12. Development of cloud-operating platform for detention facility design

    Science.gov (United States)

    Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

    2017-04-01

    In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

  13. Storage of LWR spent fuel in air: Volume 1: Design and operation of a spent fuel oxidation test facility

    International Nuclear Information System (INIS)

    Thornhill, C.K.; Campbell, T.K.; Thornhill, R.E.

    1988-12-01

    This report describes the design and operation and technical accomplishments of a spent-fuel oxidation test facility at the Pacific Northwest Laboratory. The objective of the experiments conducted in this facility was to develop a data base for determining spent-fuel dry storage temperature limits by characterizing the oxidation behavior of light-water reactor (LWR) spent fuels in air. These data are needed to support licensing of dry storage in air as an alternative to spent-fuel storage in water pools. They are to be used to develop and validate predictive models of spent-fuel behavior during dry air storage in an Independent Spent Fuel Storage Installation (ISFSI). The present licensed alternative to pool storage of spent fuel is dry storage in an inert gas environment, which is called inerted dry storage (IDS). Licensed air storage, however, would not require monitoring for maintenance of an inert-gas environment (which IDS requires) but does require the development of allowable temperature limits below which UO 2 oxidation in breached fuel rods would not become a problem. Scoping tests at PNL with nonirradiated UO 2 pellets and spent-fuel fragment specimens identified the need for a statistically designed test matrix with test temperatures bounding anticipated maximum acceptable air-storage temperatures. This facility was designed and operated to satisfy that need. 7 refs

  14. Evaluation of seismic criteria used in design of INEL facilities

    Energy Technology Data Exchange (ETDEWEB)

    Young, G.A.

    1977-09-30

    This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities. (JSR)

  15. Evaluation of seismic criteria used in design of INEL facilities

    International Nuclear Information System (INIS)

    Young, G.A.

    1977-01-01

    This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities

  16. 9 CFR 590.548 - Drying, blending, packaging, and heat treatment rooms and facilities.

    Science.gov (United States)

    2010-01-01

    ... rooms shall be well-lighted and have ceilings and walls of a tile surface, enamel paint, or other water... and accessories. (b) Dry blending of edible egg products, including adding edible dry ingredients, and/or packaging of spray-dried products shall be done in a room separate from other processing...

  17. Integration of Succinic Acid Production in a Dry Mill Ethanol Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    2006-08-01

    This project seeks to address both issues for a dry mill ethanol biorefinery by lowering the cost of sugars with the development of an advanced pretreatment process, improving the economics of succinic acid (SA), and developing a model of an ethanol dry mill to evaluate the impact of adding different products and processes to a dry mill.

  18. The effect of dryer load on freeze drying process design.

    Science.gov (United States)

    Patel, Sajal M; Jameel, Feroz; Pikal, Michael J

    2010-10-01

    Freeze-drying using a partial load is a common occurrence during the early manufacturing stages when insufficient amounts of active pharmaceutical ingredient (API) are available. In such cases, the immediate production needs are met by performing lyophilization with less than a full freeze dryer load. However, it is not obvious at what fractional load significant deviations from full load behavior begin. The objective of this research was to systematically study the effects of variation in product load on freeze drying behavior in laboratory, pilot and clinical scale freeze-dryers. Experiments were conducted with 5% mannitol (high heat and mass flux) and 5% sucrose (low heat and mass flux) at different product loads (100%, 50%, 10%, and 2%). Product temperature was measured in edge as well as center vials with thermocouples. Specific surface area (SSA) was measured by BET gas adsorption analysis and residual moisture was measured by Karl Fischer. In the lab scale freeze-dryer, the molar flux of inert gas was determined by direct flow measurement using a flowmeter and the molar flux of water vapor was determined by manometric temperature measurement (MTM) and tunable diode laser absorption spectroscopy (TDLAS) techniques. Comparative pressure measurement (capacitance manometer vs. Pirani) was used to determine primary drying time. For both 5% mannitol and 5% sucrose, primary drying time decreases and product temperature increases as the load on the shelves decreases. No systematic variation was observed in residual moisture and vapor composition as load decreased. Further, SSA data suggests that there are no significant freezing differences under different load conditions. Independent of dryer scale, among all the effects, variation in radiation heat transfer from the chamber walls to the product seems to be the dominant effect resulting in shorter primary drying time as the load on the shelf decreases (i.e., the fraction of edge vials increases).

  19. Design of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

    2001-05-01

    We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system.

  20. Design of safeguards information treatment system at the facility level

    International Nuclear Information System (INIS)

    Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

    2001-05-01

    We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system

  1. Adaptation of the ITER facility design to a Canadian site

    International Nuclear Information System (INIS)

    Smith, S.

    2001-01-01

    This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

  2. Conceptual design criteria for facilities for geologic disposal of radioactive wastes in salt formations

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The facility design requirements and criteria discussed are: general codes, standards, specifications, and regulations; site criteria; land improvements criteria, low-level waste facility criteria; canistered waste facility criteria; support facilities criteria; and utilities and services criteria. (LK)

  3. Earthquake resistant design of nuclear facilities with limited radioactive inventory

    International Nuclear Information System (INIS)

    1985-10-01

    This document comprises the essential elements of an earthquake resistant design code for nuclear facilities with limited radioactive inventory. The purpose of the document is the enhancement of seismic safety for such facilities without the necessity to resort to complicated and sophisticated methodologies which are often associated with and borrowed from nuclear power plant analysis and design. The first two sections are concerned with the type of facility for which the document is applicable and the radiological consideration for accident conditions. The principles of facility classification and item categorization as a function of the potential radiological consequences of failure are given in section 3. The design basis ground motion is evaluated in sections 4-6 using a simplified but conservative approach which also includes considerations for the underlying soil characteristics. Sections 7 and 8 specify the principles of seismic design of building structures and equipment using two methods, called the equivalent static and simplified dynamic approach. Considerations for the detailing of equipment and piping and those other than for lateral load calculations, such as sloshing effects, are given in the subsequent sections. Several appendices are given for illustration of the principles presented in the text. Finally, a design tree diagram is included to facilitate the user's task of making the appropriate selections. (author)

  4. Proceedings of the Advanced Hadron Facility accelerator design workshop

    International Nuclear Information System (INIS)

    Thiessen, H.A.

    1989-01-01

    The International Workshop on Hadron Facility Technology was held February 22-27, 1988, at the Study Center at Los Alamos National Laboratory. The program included papers on facility plans, beam dynamics, and accelerator hardware. The parallel sessions were particularly lively with discussions of all facets of kaon factory design. The workshop provided an opportunity for communication among the staff involved in hadron facility planning from all the study groups presently active. The recommendations of the workshop include: the need to use h=1 RF in the compressor ring; the need to minimize foil hits in painting schemes for all rings; the need to consider single Coulomb scattering in injection beam los calculations; the need to study the effect of field inhomogeneity in the magnets on slow extraction for the 2.2 Tesla main ring of AHF; and agreement in principle with the design proposed for a joint Los Alamos/TRIUMF prototype main ring RF cavity

  5. Design and construction innovations of the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    McKibben, J.M.; Pair, C.R.; Bethmann, H.K.

    1990-01-01

    Construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is essentially complete. The facility is designed to convert high level radioactive waste, now contained in large steel tanks as aqueous salts and sludge, into borosilicate glass which will solidify in stainless steel canisters. All processing of the radioactive material and operations in a radioactive environment will be done remotely. The stringent requirements dictated by remote operation and new approaches to the glassification process led to the development of a number of first-of-a-kind pieces of equipment, new construction fabrication and erection techniques, and new applications of old techniques. The design features and construction methods used in the vitrification building and its equipment were to accomplish the objective of providing a state-of-the-art vitrification facility. 3 refs., 10 figs

  6. Gas cooled fast breeder reactor design for a circulator test facility (modified HTGR circulator test facility)

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    A GCFR helium circulator test facility sized for full design conditions is proposed for meeting the above requirements. The circulator will be mounted in a large vessel containing high pressure helium which will permit testing at the same power, speed, pressure, temperature and flow conditions intended in the demonstration plant. The electric drive motor for the circulator will obtain its power from an electric supply and distribution system in which electric power will be taken from a local utility. The conceptual design decribed in this report is the result of close interaction between the General Atomic Company (GA), designer of the GCFR, and The Ralph M. Parson Company, architect/engineer for the test facility. A realistic estimate of total project cost is presented, together with a schedule for design, procurement, construction, and inspection.

  7. The design of diagnostic medical facilities using ionizing radiation

    International Nuclear Information System (INIS)

    1988-03-01

    This Code, setting out the general principles of radiological protection as applied to diagnostic radiation facilities in hospitals and clinics, is intended as a guide to architects and to works departments concerned with their design and construction, and with the modification of existing units

  8. Tools for Stakeholder Involvement in Facility Management Service Design

    DEFF Research Database (Denmark)

    Nardelli, Giulia; Scupola, Ada

    Purpose: The purpose of this paper is to provide an overview of the tools that Facility Management (FM) companies use to involve different stakeholders, and more precisely the ones on the demand side, in the FM service design process. Stakeholder involvement may contribute to FM service innovatio...

  9. Neutron streaming analysis for shield design of FMIT Facility

    International Nuclear Information System (INIS)

    Carter, L.L.

    1980-12-01

    Applications of the Monte Carlo method have been summarized relevant to neutron streaming problems of interest in the shield design for the FMIT Facility. An improved angular biasing method has been implemented to further optimize the calculation of streaming and this method has been applied to calculate streaming within a double bend pipe

  10. Design guides for radioactive-material-handling facilities and equipment

    International Nuclear Information System (INIS)

    Doman, D.R.; Barker, R.E.

    1980-01-01

    Fourteen key areas relating to facilities and equipment for handling radioactive materials involved in examination, reprocessing, fusion fuel handling and remote maintenance have been defined and writing groups established to prepare design guides for each areas. The guides will give guidance applicable to design, construction, operation, maintenance and safety, together with examples and checklists. Each guide will be reviewed by an independent review group. The guides are expected to be compiled and published as a single document

  11. Properties of radioisotope sources and design of irradiation facilities

    International Nuclear Information System (INIS)

    Kasamatsu, Tomomichi

    1976-01-01

    Radioisotope sources for industrial use are described, and irradiation facilities are also explained. The materials considered for radiation sources are Co-60, Cs-137, Sr-90, Kr-85, fission products and spent fuel. The dose rate distribution of radiation sources is important for the design of irradiation facilities. The sources must be placed into lead containers and installed in shielded rooms. It is easy to construct the facility for the source of a small amount. The facility and equipments for the source of a large amount must be designed carefully according to the purpose. Examples are illustrated. The cost for irradiation is also an important factor to be considered for industrial use. The amount of required dose, the sizes of apparatuses and containers, the amount of gamma-ray sources and so on are considered in the estimation. The regulation standard for radiation safety is determined by a law. The radiation sources should be sealed completely. Radiation shielding from the sealed sources, the principles of handling the sources, the facilities for handling the sealed sources, the management of the sealed sources and the health check-up of workmen are prescribed. (Kato, T.)

  12. Requirements and design concept for a facility mapping system

    International Nuclear Information System (INIS)

    Barry, R.E.; Burks, B.L.; Little, C.Q.

    1995-01-01

    The Department of Energy (DOE) has for some time been considering the Decontamination and Dismantlement (D ampersand D) of facilities which are no longer in use, but which are highly contaminated with radioactive wastes. One of the holdups in performing the D ampersand D task is the accumulation of accurate facility characterizations that can enable a safe and orderly cleanup process. According to the Technical Strategic Plan for the Decontamination and Decommissioning Integrated Demonstration, open-quotes the cost of characterization using current baseline technologies for approximately 100 acres of gaseous diffusion plant at Oak Ridge alone is, for the most part incalculableclose quotes. Automated, robotic techniques will be necessary for initial characterization and continued surveillance of these types of sites. Robotic systems are being designed and constructed to accomplish these tasks. This paper describes requirements and design concepts for a system to accurately map a facility contaminated with hazardous wastes. Some of the technologies involved in the Facility Mapping System are: remote characterization with teleoperated, sensor-based systems, fusion of data sets from multiple characterization systems, and object recognition from 3D data models. This Facility Mapping System is being assembled by Oak Ridge National Laboratory for the DOE Office of Technology Development Robotics Technology Development Program

  13. An ARM Mobile Facility Designed for Marine Deployments

    Science.gov (United States)

    Wiscombe, W. J.

    2007-05-01

    The U.S. Dept. of Energy's ARM (Atmospheric Radiation Measurements) Program is designing a Mobile Facility exclusively for marine deployments. This marine facility is patterned after ARM's land Mobile Facility, which had its inaugural deployment at Point Reyes, California, in 2005, followed by deployments to Niger in 2006 and Germany in 2007 (ongoing), and a planned deployment to China in 2008. These facilities are primarily intended for the study of clouds, radiation, aerosols, and surface processes with a goal to include these processes accurately in climate models. They are preferably embedded within larger field campaigns which provide context. They carry extensive instrumentation (in several large containers) including: cloud radar, lidar, microwave radiometers, infrared spectrometers, broadband and narrowband radiometers, sonde-launching facilities, extensive surface aerosol measurements, sky imagers, and surface latent and sensible heat flux devices. ARM's Mobile Facilities are designed for 6-10 month deployments in order to capture climatically-relevant datasets. They are available to any scientist, U.S. or international, who wishes to submit a proposal during the annual Spring call. The marine facility will be adapted to, and ruggedized for, the harsh marine environment and will add a scanning two-frequency radar, a boundary-layer wind profiler, a shortwave spectrometer, and aerosol instrumentation adapted to typical marine aerosols like sea salt. Plans also include the use of roving small UAVs, automated small boats, and undersea autonomous vehicles in order to address the point-to-area-average problem which is so crucial for informing climate models. Initial deployments are planned for small islands in climatically- interesting cloud regimes, followed by deployments on oceanic platforms (like decommissioned oil rigs and the quasi-permanent platform of this session's title) and eventually on large ships like car carriers plying routine routes.

  14. Design of good manufacturing facility for sterile radioactive pharmaceuticals

    International Nuclear Information System (INIS)

    Shin, B.C.; Choung, W.M.; Park, S.H.; Lee, K.I.; Park, J.H.; Park, K.B.

    2002-01-01

    Based on the GMP codes for radiopharmaceuticals in U.K. and some advanced countries, suitable guidelines for the production facility have been established and followed them up. The facility designs were fairly modified to maintain cleanliness criteria for installation in the existing radioisotope production facilities which are installed only in radiation safety points of view. Detailed design brief was drawn up by the Hyundai Engineering staffs, on the basis of initial planning and conceptual design was carried out by authors. Hot cells were installed in preparation room for radioactive handling. As hot cells under negative air pressure are not properly airtight, the surrounding environment was designed to keep less than class 10,000. Hot cells were designed to maintain less than class 1 0,000 and partially less than class 1 00 for production of sterile products. Final products will be autoclaved for sterilization after filling. To avoid contamination by microorganisms and particles of surrounding area, air curtain with vertical laminar flow will be installed between anteroom and corridor. In a pharmaceutical environment, the main consideration is the protection of the product. Thus, work station is held above ambient pressure. However, when handling radioactive materials, air pressure for work station should be lower than in surrounding areas to protect the operators and the remainder of the facility from airborne radioactive contamination. As Radiopharmaceuticals are radioactive materials for medical use, changing room could be held higher pressure than any other zones. It is expected that the facility will be effectively used for both routine preparation and research for sterile radiopharmaceuticals. (Author)

  15. GNS Experience on the Long-Term Storage at Dry Interim Storage Facilities Especially in Ahaus and Gorleben

    International Nuclear Information System (INIS)

    Oelschlaeger, Lutz; Heck, Matthias; Graf, Wilhelm

    2014-01-01

    This presentation provides a general overview on the operation experience of the dry interim storage facilities in Ahaus and Gorleben (later referred to as TBL-A and TBL-G). GNS is solely in charge of the operation and maintenance of both facilities licensed for a dry storage period of 40 years. The amount of different cask types stored to date which are loaded with spent fuel and reprocessing waste and the cask specific information such as heat capacity, heat flow and dose rate are shown. A presentation of the transport and storage operation experience (e. g. statistics of the monitoring system) follows as well as an outlook on future activities. The associated licensing procedures are outlined in view of pre-existing licenses together with present or future licensing activities. This includes cask approval procedures according to the international safety requirements for transport and licensing procedures as laid down in the German Atomic Act. Both facilities have been operated, to a large extent, independently of nuclear power plants. Different casks have been stored there for more than ten years. In terms of best practices the vast operational experience gathered at these interim storage facilities is shown on practical examples i.e. the 10-year cask inspection, the pilot process for the periodical safety review as well as the ageing management demonstrating the robustness of the dry cask storage concept. The key aspects of the GNS expertise and a summary of the GNS position as well as perspectives for the long-term dry storage complete the presentation. (authors)

  16. Key points for the design of Mox facilities

    International Nuclear Information System (INIS)

    Ducroux, R.; Gaiffe, L.; Dumond, S.; Cret, L.

    1998-01-01

    The design of a MOX fuel fabrication facility involves specific technical difficulties: - Process aspects: for example, its is necessary to meet the stringent requirements on the end products, while handling large quantities of powders and pellets; - Safety aspects: for example, containment of radioactive materials requires to use gloveboxes, to design process equipment so as to limit dispersion to the gloveboxes and to use systems for dust collection. - Technological aspects: for example, it is necessary to take into account maintenance early in the design, in order to lower the operation costs and lower the dose to the personnel. - Quality control and information systems: for example, it is necessary to be able to trace all the different products (powder lots, pellets, rods, assemblies). The design methods and organization set-up by COGEMA enables to master these technical difficulties during the different design steps and to obtain a MOX fabrication facility at the best performance versus cost compromise. These design methods rely mainly on: - taking into account all the different above mentioned constraints from the very beginning of the design process (by using the know-how resulting from experience feed-back, and also specific design tools developed by COGEMA and SGN); - launching a technical development and testing program at the beginning of the project and incorporating its results in the course of the design. (author)

  17. Waste receiving and processing facility module 1, detailed design report

    International Nuclear Information System (INIS)

    1993-10-01

    WRAP 1 baseline documents which guided the technical development of the Title design included: (a) A/E Statement of Work (SOW) Revision 4C: This DOE-RL contractual document specified the workscope, deliverables, schedule, method of performance and reference criteria for the Title design preparation. (b) Functional Design Criteria (FDC) Revision 1: This DOE-RL technical criteria document specified the overall operational criteria for the facility. The document was a Revision 0 at the beginning of the design and advanced to Revision 1 during the tenure of the Title design. (c) Supplemental Design Requirements Document (SDRD) Revision 3: This baseline criteria document prepared by WHC for DOE-RL augments the FDC by providing further definition of the process, operational safety, and facility requirements to the A/E for guidance in preparing the design. The document was at a very preliminary stage at the onset of Title design and was revised in concert with the results of the engineering studies that were performed to resolve the numerous technical issues that the project faced when Title I was initiated, as well as, by requirements established during the course of the Title II design

  18. Mixture design applied to optimize a directly compressible powder produced via cospray drying.

    Science.gov (United States)

    Gonnissen, Yves; Gonçalves, Sara Isabel Vieira; Remon, Jean Paul; Vervaet, Chris

    2008-03-01

    Coprocessing via spray drying was applied to improve the compactability of acetaminophen and to select an optimal formulation. Four-component mixtures containing acetaminophen, mannitol, erythritol, and maltodextrin were produced by cospray drying. A D-optimal mixture design was constructed to evaluate the spray dried powder and tablet properties. An increasing mannitol and erythritol content improved powder flowability and density. However, a higher erythritol concentration in the spray dried powder mixture had a negative influence on tablet tensile strength and friability. A higher maltodextrin content increased tablet tensile strength and improved tablet friability, while disintegration time, average particle size, powder flowability, density, and hygroscopicity were negatively influenced.

  19. Engineering spray-dried rosemary extracts with improved physicomechanical properties: a design of experiments issue

    Directory of Open Access Journals (Sweden)

    Luiza T. Chaul

    Full Text Available ABSTRACT A 33 Box–Behnken design and Response Surface Methodology were performed to evaluate the influence of extract feed rate, drying air inlet temperature and spray nozzle airflow rate on the process yield, stability parameters (moisture content and water activity and on several physicomechanical properties of spray-dried rosemary extracts. Powder yield ranged from 17.1 to 74.96%. The spray-dried rosemary extracts showed moisture content and water activity below 5% and 0.5%, respectively, which indicate their chemical and microbiological stabilities. Even without using drying aids, some sets of experimental conditions rendered dried products with suitable flowability and compressibility characteristics for direct preparation of solid dosage forms. Analysis of variance and Response Surface Methodology proved that studied factors significantly affected most of the spray-dried rosemary extract quality indicators at different levels. The main processing parameter affecting the spray-dried rosemary extract characteristics was inlet temperature. The best combination of parameters used to obtain a reasonable yield of stable dry rosemary extracts with adequate technological properties for pharmaceutical purpose involves an extract feed rate of 2 ml/min, 80 °C inlet temperature and 40 l/min SA. The design of experiments approach is an interesting strategy for engineering spray-dried rosemary extracts with improved characteristics for pharmaceutical industrial purpose.

  20. Biological shielding design calculation for agricultural radiation processing facility

    International Nuclear Information System (INIS)

    Petwal, V.C.; Sandha, R.S.; Soni, H.C.; Subbaiah, K.V.

    2005-01-01

    An electron beam radiation processing facility for agricultural products is being set-up at Centre for Advanced Technology Indore. The facility will be based on a pulsed linear accelerator and will be used in electron and photon modes to process various products e.g. onion, potato, home-pack items and medical products. When electron beam interact with structural components of accelerator or high Z-target used in photon mode, it generates intense Bremsstrahlung radiation field, which poses radiation protection problem. Biological shielding has been designed to provide protection against the generated radiation. Different conveying schemes and hence design of irradiation cell have been studied and results are presented for two promising designs. (author)

  1. Design characteristics for facilities which process hazardous particulate

    Energy Technology Data Exchange (ETDEWEB)

    Abeln, S.P.; Creek, K.; Salisbury, S.

    1998-12-01

    Los Alamos National Laboratory is establishing a research and processing capability for beryllium. The unique properties of beryllium, including light weight, rigidity, thermal conductivity, heat capacity, and nuclear properties make it critical to a number of US defense and aerospace programs. Concomitant with the unique engineering properties are the health hazards associated with processing beryllium in a particulate form and the potential for worker inhalation of aerosolized beryllium. Beryllium has the lowest airborne standard for worker protection compared to all other nonradioactive metals by more than an order of magnitude. This paper describes the design characteristics of the new beryllium facility at Los Alamos as they relate to protection of the workforce. Design characteristics to be reviewed include; facility layout, support systems to minimize aerosol exposure and spread, and detailed review of the ventilation system design for general room air cleanliness and extraction of particulate at the source.

  2. Design of a test facility for probe calibration

    Directory of Open Access Journals (Sweden)

    Šimák Jan

    2017-01-01

    Full Text Available A possibility to easily calibrate probes for flow field measurements is always welcome. From this reason, a design of a test facility for probe calibration was made. The probes will be calibrated in a free jet of known properties, which is created by an exchangeable nozzle to cover a wide range of Mach numbers up to Mach 2. The most important is to create a homogeneous flow across the test section. This is accomplished by a precise design of the nozzles carried out by numerical tools. The convergent nozzle part is common for all subsonic flow regimes while the divergent part (forming a de Laval nozzle is suited for a specific supersonic Mach number. These parts are designed using the method of characteristics. Numerical simulations performed by a CFD code show a feasibility and quality of the proposed test facility.

  3. A Dry-Slip Facility for Fish Terminals on Open Coasts

    DEFF Research Database (Denmark)

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

    conventional harbours, and it represents an alternative to such harbours on coasts where littoral drift causes serious sedimentation and erosion. A proposal for a special device called "the dry-slip" for lifting fishing boats out of the water in bad weather situations is made. The dry-slip system was tested...

  4. Proposed design criteria for a fusion facility electrical ground system

    International Nuclear Information System (INIS)

    Armellino, C.A.

    1983-01-01

    Ground grid design considerations for a nuclear fusion reactor facility are no different than any other facility in that the basis for design must be safety first and foremost. Unlike a conventional industrial facility the available fault energy comes not only from the utility source and in-house rotating machinery, but also from energy storage capacitor banks, collapsing magnetic fields and D.C. transmission lines. It is not inconceivable for a fault condition occurrence where all available energy can be discharged. The ground grid must adequately shunt this sudden energy discharge in a way that personnel will not be exposed by step and/or touch to hazardous energy levels that are in excess of maximum tolerable levels for humans. Fault energy discharge rate is a function of the ground grid surge impedance characteristic. Closed loop paths must be avoided in the ground grid design so that during energy discharge no stray magnetic fields or large voltage potentials between remote points can be created by circulating currents. Single point connection of equipment to the ground grid will afford protection to personnel and sensitive equipment by reducing the probability of circulating currents. The overall ground grid system design is best illustrated as a wagon wheel concept with the fusion machine at the center. Radial branches or spokes reach out to the perimeter limits designated by step-and-touch high risk areas based on soil resistivity criteria considerations. Conventional methods for the design of a ground grid with all of its radial branches are still pertinent. The center of the grid could include a deep well single ground rod element the length of which is at least equivalent to the radius of an imaginary sphere that enshrouds the immediate machine area. Special facilities such as screen rooms or other shielded areas are part of the ground grid system by way of connection to radial branches

  5. Methods and techniques for decontamination design and construction of facilities

    International Nuclear Information System (INIS)

    Augustin, X.; Cohen, S.

    1986-01-01

    TECHNICATOME and STMI have jointly solved a wide range of problems specific to decontamination from the very design studies up to operation. TECHNICATOME has brought its expertise in the design and construction of nuclear facilities concerned in particular with decontamination and radwaste management. STMI is an experienced operator with expertise in designing tools and developing advanced techniques in the same fields. The expertise of both companies in this field cumulated for many years has resulted in developing techniques and tools adapted to most of the decontamination problems including specific cases [fr

  6. Design of Pump as Turbine Experimental Test Facility

    Directory of Open Access Journals (Sweden)

    Zariatin D. L.

    2017-01-01

    Full Text Available This paper presents the design process of experimental test facility for pump as turbine hydropower system. Three design possibilities that related to the PAT condition of operation was developed and analyzed by using CFD Software. It is found that the First Variant with a straight flow to the PAT will produce higher velocity, which is needed to generate more rotation of the shaft generator, in order to generate more electric power. The strength of PAT construction was analyzed by using FEM software. It was found that the maximum stress is 6 MPa and can be concluded that the construction is appropriate to the design requirement.

  7. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

    Singh, M.S.; Campbell, G.W.

    1982-01-01

    The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

  8. Drying of water based foundry coatings: Innovative test, process design and optimization methods

    DEFF Research Database (Denmark)

    Di Muoio, Giovanni Luca; Johansen, Bjørn Budolph

    Director Bjørn Budolph Johansen has been the company supervisor from March 2012 to June 2014. In this Industrial PhD Thesis we present the main results of several tests and simulations carried out from 2011 to 2014 at Global Castings A/S (former Vestas Wind Systems A/S) and at the Technical University...... capacity goals there is a need to understand how to design, control and optimize drying processes. The main focus of this project was on the critical parameters and properties to be controlled in production in order to achieve a stable and predictable drying process. We propose for each of these parameters...... on real industrial cases. These tools have been developed in order to simulate and optimize the drying process and reduce drying time and power consumption as well as production process design time and cost of expensive drying equipment. Results show that test methods from other industries can be used...

  9. Towards a design theory for reducing aggression in psychiatric facilities

    DEFF Research Database (Denmark)

    Ulrich, Roger S; Bogren, Lennart; Lundin, Stefan

    2012-01-01

    The paper proposes a tentative theory for designing psychiatric environments to foster reduced aggression and violence. A basic premise underlying the design theory is that environmental and psycho-social stressors mediate and trigger aggression. The theory posits that aggression will be reduced ...... buildings with design guided by the best available evidence and theory can play an important role in reducing the serious patient and staff safety problem of aggressive behavior.......The paper proposes a tentative theory for designing psychiatric environments to foster reduced aggression and violence. A basic premise underlying the design theory is that environmental and psycho-social stressors mediate and trigger aggression. The theory posits that aggression will be reduced...... if the facility has been designed with an evidence-based bundle of stress-reducing environmental characteristics that are identified and discussed. To make possible a tentative empirical evaluation of the theory, findings are described from a study that compared aggressive incidents in three Swedish psychiatric...

  10. Urbanonymic Design: On the Naming of City Facilities

    Directory of Open Access Journals (Sweden)

    Marina V. Golomidova

    2015-06-01

    Full Text Available The paper focuses on the problems of naming and renaming of municipal facilities: streets, squares, parks, public gardens, etc. The author’s reflections rest upon her personal experience as a member of the Facilities Naming Committee of the city of Ekaterinburg. The article seeks to suggest a new approach to the solution of controversial issues of naming city facilities based on territory branding and city image design and promotion concepts. Place names are thus considered as an important informational and communicational resource of creation of a city’s image which means that the naming of concrete city facilities should rely on a holistic urbanonymic conception defining basic features of the city’s identity and ordering themes to be reflected in names. The author argues that the rational long-term urbanonymic policy implies the existence of a consistent image-making strategy. In this case the process of naming and its results could be characterized in terms of ‘urbanonymic design’ considering the naming of city facilities as a part of the construction of the city’s identity. The policy of official naming of city-owned assets must then meet the following requirements: proportionality, functionality, orientation capacity, semantic transparency, harmonicity, which constitute the most significant principles of construction of an urbanonymic system.

  11. Sound & Vibration 20 Design Guidelines for Health Care Facilities

    CERN Document Server

    Tocci, Gregory; Cavanaugh, William

    2013-01-01

    Sound, vibration, noise and privacy have significant impacts on health and performance. As a result, they are recognized as essential components of effective health care environments. However, acoustics has only recently become a prominent consideration in the design, construction, and operation of healthcare facilities owing to the absence, prior to 2010, of clear and objective guidance based on research and best practices. Sound & Vibration 2.0 is the first publication to comprehensively address this need. Sound & Vibration 2.0 is the sole reference standard for acoustics in health care facilities and is recognized by: the 2010 FGI Guidelines for the Design and Construction of Health Care Facilities (used in 60 countries); the US Green Building Council’s LEED for Health Care (used in 87 countries); The Green Guide for Health Care V2.2; and the International Code Council (2011). Sound & Vibration 2.0 was commissioned by the Facility Guidelines Institute in 2005, written by the Health Care Acous...

  12. Humidifying system design of PEMFC test platform based on the mixture of dry and wet air

    Directory of Open Access Journals (Sweden)

    Tiancai Ma

    2015-01-01

    Full Text Available Based on the present humidifying system of PEMFC test platform, a novel design based on dry and wet air mixture is proposed. Key parameters are calculated, and test platform is built. Three experiments are implemented to test the performance of proposed design. Results show that the new design can meet the requirements, and realize the quick response and accurate control.

  13. Advanced Energy Design Guide for Small Hospitals and Healthcare Facilities

    Directory of Open Access Journals (Sweden)

    Eric Bonnema

    2010-01-01

    Full Text Available The Advanced Energy Design Guide for Small Hospitals and Healthcare Facilities (AEDG-SHC was recently completed. It is the sixth document in a series of guides designed to achieve 30% savings over the minimum code requirements of ANSI/ASHRAE/IESNA Standard 90.1-1999. The guide [1] is available for print purchase or as a free download from http://www.ashrae.org/aedg and provides user-friendly assistance and recommendations for the building design, construction, and owner communities to achieve energy savings. Included in the guide are prescriptive recommendations for quality assurance and commissioning; design of the building envelope; fenestration; lighting systems (including electric lighting and daylighting; heating, ventilation, and air-conditioning (HVAC systems; building automation and controls; outside air (OA treatment; and service water heating (SWH. The guide educates, provides practical recommendations for exceeding code minimums, and provides leadership to help design teams and owners produce higher efficiency commercial buildings.

  14. Shielding Design and Radiation Shielding Evaluation for LSDS System Facility

    International Nuclear Information System (INIS)

    Kim, Younggook; Kim, Jeongdong; Lee, Yongdeok

    2015-01-01

    As the system characteristics, the target in the spectrometer emits approximately 1012 neutrons/s. To efficiently shield the neutron, the shielding door designs are proposed for the LSDS system through a comparison of the direct shield and maze designs. Hence, to guarantee the radiation safety for the facility, the door design is a compulsory course of the development of the LSDS system. To improve the shielding rates, 250x250 covering structure was added as a subsidiary around the spectrometer. In this study, the evaluations of the suggested shielding designs were conducted using MCNP code. The suggested door design and covering structures can shield the neutron efficiently, thus all evaluations of all conditions are satisfied within the public dose limits. From the Monte Carlo code simulation, Resin(Indoor type) and Tungsten(Outdoor type) were selected as the shielding door materials. From a comparative evaluation of the door thickness, In and Out door thickness was selected 50 cm

  15. Freeze-drying process design by manometric temperature measurement: design of a smart freeze-dryer.

    Science.gov (United States)

    Tang, Xiaolin Charlie; Nail, Steven L; Pikal, Michael J

    2005-04-01

    To develop a procedure based on manometric temperature measurement (MTM) and an expert system for good practices in freeze drying that will allow development of an optimized freeze-drying process during a single laboratory freeze-drying experiment. Freeze drying was performed with a FTS Dura-Stop/Dura-Top freeze dryer with the manometric temperature measurement software installed. Five percent solutions of glycine, sucrose, or mannitol with 2 ml to 4 ml fill in 5 ml vials were used, with all vials loaded on one shelf. Details of freezing, optimization of chamber pressure, target product temperature, and some aspects of secondary drying are determined by the expert system algorithms. MTM measurements were used to select the optimum shelf temperature, to determine drying end points, and to evaluate residual moisture content in real-time. MTM measurements were made at 1 hour or half-hour intervals during primary drying and secondary drying, with a data collection frequency of 4 points per second. The improved MTM equations were fit to pressure-time data generated by the MTM procedure using Microcal Origin software to obtain product temperature and dry layer resistance. Using heat and mass transfer theory, the MTM results were used to evaluate mass and heat transfer rates and to estimate the shelf temperature required to maintain the target product temperature. MTM product dry layer resistance is accurate until about two-thirds of total primary drying time is over, and the MTM product temperature is normally accurate almost to the end of primary drying provided that effective thermal shielding is used in the freeze-drying process. The primary drying times can be accurately estimated from mass transfer rates calculated very early in the run, and we find the target product temperature can be achieved and maintained with only a few adjustments of shelf temperature. The freeze-dryer overload conditions can be estimated by calculation of heat/mass flow at the target product

  16. Basic Design of the Cold Neutron Research Facility in HANARO

    International Nuclear Information System (INIS)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K.

    2005-09-01

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments

  17. Basic Design of the Cold Neutron Research Facility in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K. (and others)

    2005-09-15

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments.

  18. Mortality monitoring design for utility-scale solar power facilities

    Science.gov (United States)

    Huso, Manuela; Dietsch, Thomas; Nicolai, Chris

    2016-05-27

    IntroductionSolar power represents an important and rapidly expanding component of the renewable energy portfolio of the United States (Lovich and Ennen, 2011; Hernandez and others, 2014). Understanding the impacts of renewable energy development on wildlife is a priority for the U.S. Fish and Wildlife Service (FWS) in compliance with Department of Interior Order No. 3285 (U.S. Department of the Interior, 2009) to “develop best management practices for renewable energy and transmission projects on the public lands to ensure the most environmentally responsible development and delivery of renewable energy.” Recent studies examining effects of renewable energy development on mortality of migratory birds have primarily focused on wind energy (California Energy Commission and California Department of Fish and Game, 2007), and in 2012 the FWS published guidance for addressing wildlife conservation concerns at all stages of land-based wind energy development (U.S. Fish and Wildlife Service, 2012). As yet, no similar guidelines exist for solar development, and no published studies have directly addressed the methodology needed to accurately estimate mortality of birds and bats at solar facilities. In the absence of such guidelines, ad hoc methodologies applied to solar energy projects may lead to estimates of wildlife mortality rates that are insufficiently accurate and precise to meaningfully inform conversations regarding unintended consequences of this energy source and management decisions to mitigate impacts. Although significant advances in monitoring protocols for wind facilities have been made in recent years, there remains a need to provide consistent guidance and study design to quantify mortality of bats, and resident and migrating birds at solar power facilities (Walston and others, 2015).In this document, we suggest methods for mortality monitoring at solar facilities that are based on current methods used at wind power facilities but adapted for the

  19. Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Fattor, Steven [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2014-06-01

    The manual contains general requirements that apply to nonnuclear and nonexplosive facilities. For design and construction requirements for modifications to nuclear or explosive facilities, see the project-specific design requirements noted in the Design Criteria.

  20. Present status of the conceptual design of IFMIF target facility

    International Nuclear Information System (INIS)

    Katsuta, H.; Kato, Y.; Konishi, S.; Miyauchi, Y.; Smith, D.; Hua, T.; Green, L.; Benamati, G.; Cevolani, S.; Roehrig, H.; Schutz, W.

    1998-01-01

    The conceptual design activity (CDA) for the international fusion materials irradiation facility (IFMIF) has been conducted. For the IFMIF target facility, the conceptual designs of the following two main components have been performed. The design concept of IFMIF utilizes a high energy deuteron beam of 30-40 MeV and total current of 250 mA, impinging on a flowing lithium jet to produce high energy neutrons for irradiation of candidate fusion materials. (1) The target assembly: The kinetic energy of the deuteron beam is deposited on a Li-jet target and neutrons are produced through the d-Li stripping reaction in this target. The assembly is designed to get a stable lithium jet and to prevent the onset of lithium boiling. For 40-MeV deuteron beam (total current of 250 mA) and a beam footprint of 5 x 20 cm 2 lithium jet dimensions are designed to be 2.5 cm thick and 26 cm wide. The lithium jet parameters are given. (2) Lithium loop: The loop circulates the lithium to and from the target assembly and removes the heat deposited by the deuteron beam containing systems for maintaining the-high purity of the lithium required for radiological safety and to minimize corrosion. The maximum lithium flow rate is 130 l/s and the total lithium inventory is about 21 m 3 . The IFMIF policy requires that the lithium loop system be designed to guarantee no combustion of lithium in the event of a lithium leak. This can be achieved by use of multiple confinement of the lithium carrying components. The radioactive waste generated by the target facilities is estimated. (orig.)

  1. Design of a drying system for a rollover carwash machine using CFD

    Directory of Open Access Journals (Sweden)

    Seyyed M.M. Sabet

    2016-10-01

    Full Text Available This work describes the design and development of a new drying system for a rollover carwash machine with the support of numerical tools. The drying system is composed of a pair of stationary vertical dryers and a moveable horizontal dryer that can adjust itself to the contour of a vehicle. After the definition of the dryers’ concept, their performance was assessed individually to check their internal flow pattern and to improve their airflow distribution. These issues are expected to provide feedback on redesign and geometric optimization of the dryers. After redesign of the dryers separately, the behaviour of the complete drying system was studied on actual vehicle models, representative of the shortest and tallest dimensions that can be washed with the existing carwash machine sector. The drying efficiency of the whole system was studied by calculation of shear stress distribution on various surfaces of a given vehicle. The results allowed concluding that the overall drying performance of the design system is very good and assure adequate drying on most vehicles surfaces. The results obtained from numerical studies were then validated with experimental measurements and a good agreement was found between the two. The procedure employed in this work can be applied to support the design and analysis of other mechanical drying systems.

  2. Development of the safety case for a spent fuel dry storage facility in Kazakhstan, a case study

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, D.N.; Lambert, J.D.B.; Planchon, H.P.; Howden, E.A. [Argonne National Lab., Idaho Falls, ID (United States)

    2001-07-01

    With the decline of the Soviet Union and concomitant independence of Kazakhstan, a large amount of plutonium rich spent fuel was left at the BN-350 fast reactor in western Kazakhstan. This was a significant safeguard problem and the US and Kazakhstan jointly decided to upgrade the security of the material by placing it in safe and secure dry storage. A team of specialists from the US and Kazakhstan was formed to evaluate dry storage options and storage sites. Based on its elegant simplicity, the team selected the drywell storage concept utilized at Argonne National Laboratory. As of October 2000, the intact spent fuel assemblies from the cooling pond and reactor have been packaged for dry storage. Packaging of the spent fuel assemblies that failed during operation is in progress and will soon be completed. Packaging was performed for drywell storage but a facility has not been constructed. The Kazakhstan and US specialists are reevaluating storage options for the packaged spent fuel. The purpose of this paper is to present the safety case for a drywell storage facility as developed by Kazakhstan and the US. (authors)

  3. Skylab Medical Experiments Altitude Test /SMEAT/ facility design and operation.

    Science.gov (United States)

    Hinners, A. H., Jr.; Correale, J. V.

    1973-01-01

    This paper presents the design approaches and test facility operation methods used to successfully accomplish a 56-day test for Skylab to permit evaluation of selected Skylab medical experiments in a ground test simulation of the Skylab environment with an astronaut crew. The systems designed for this test include the two-gas environmental control system, the fire suppression and detection system, equipment transfer lock, ground support equipment, safety systems, potable water system, waste management system, lighting and power system, television monitoring, communications and recreation systems, and food freezer.

  4. Design of concrete structures important to safety of nuclear facilities

    International Nuclear Information System (INIS)

    2001-10-01

    Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. The objective and minimum requirements for the design of civil engineering buildings/structures to be fulfilled to provide adequate assurance for safety of nuclear installations in India (such as pressurised heavy water reactor and related systems) are specified in the Safety standard for civil engineering structures important to safety of nuclear facilities. This standard is written by AERB to specify guidelines for implementation of the above civil engineering safety standard in the design of concrete structures important to safety

  5. Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

    2009-09-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

  6. Design and evaluation of physical protection systems of nuclear facilities

    International Nuclear Information System (INIS)

    An, Jin Soo; Lee, Hyun Chul; Hwang, In Koo; Kwack, Eun Ho; Choi, Yung Myung

    2001-06-01

    Nuclear material and safety equipment of nuclear facilities are required to be protected against any kind of theft or sabotage. Physical protection is one of the measures to prevent such illegally potential threats for public security. It should cover all the cases of use, storage, and transportation of nuclear material. A physical protection system of a facility consists of exterior intrusion sensors, interior intrusion sensors, an alarm assessment and communication system, entry control systems, access delay equipment, etc. The design of an effective physical protection system requires a comprehensive approach in which the designers define the objective of the system, establish an initial design, and evaluate the proposed design. The evaluation results are used to determine whether or not the initial design should be modified and improved. Some modelling techniques are commonly used to analyse and evaluate the performance of a physical protection system. Korea Atomic Energy Research Institute(KAERI) has developed a prototype of software as a part of a full computer model for effectiveness evaluation for physical protection systems. The input data elements for the prototype, contain the type of adversary, tactics, protection equipment, and the attributes of each protection component. This report contains the functional and structural requirements defined in the development of the evaluation computer model

  7. An Experience of Thermowell Design in RCP Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. S.; Kim, B. D.; Youn, Y. J.; Jeon, W. J.; Kim, S.; Bae, B. U.; Cho, Y. J.; Choi, H. S.; Park, J. K; Cho, S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Flow rates for the test should vary in the range of 90% to 130% of rated flowrate under prototypic operational conditions, as shown in Table 1. Generally for the flow control, a combination of a control valve and an orifice was used in previous RCP test facilities. From the commissioning startup of the RCP test facility, it was found the combination of valve and orifice induced quite a large vibration for the RCP. As a solution to minimize the vibration and to facilitate the flowrate control, one of KAERI's staff suggested a variable restriction orifice (VRO), which controls most of the required flowrates except highest flowrates, as shown in Fig. 2. For the highest flowrates, e.g., around run-out flowrate (130%), control valves in bypass lines were also used to achieve required flowrates. From a performance test, it was found the VRO is very effective measures to control flowrates in the RCP test facility. During the commissioning startup operation, one of thermowells located at the upstream of the RCP was cracked due to high speed coolant velocity, which was - fortunately - found under a leakage test before running the RCP test loop. The cracked thermowell, whose tapered-shank was detached from the weld collar after uninstalling, is shown in Fig. 3. As can be seen the figure, most of the cross-section at the root of the thermowell shank was cracked. In this paper, an investigation of the integrity of thermowells in the RCP test facility was performed according to the current code and overall aspects on the thermowell designs were also discussed. An RCP test facility has been constructed in KAERI. During the commissioning startup operation, one of thermowells was cracked due to high speed coolant velocity. To complete the startup operation, a modified design of thermowells was proposed and all the original thermowells were replaced by the modified ones. From evaluation of the original and modified designs of thermowells according to the recent PTC code, the

  8. A stochastic discrete optimization model for designing container terminal facilities

    Science.gov (United States)

    Zukhruf, Febri; Frazila, Russ Bona; Burhani, Jzolanda Tsavalista

    2017-11-01

    As uncertainty essentially affect the total transportation cost, it remains important in the container terminal that incorporates several modes and transshipments process. This paper then presents a stochastic discrete optimization model for designing the container terminal, which involves the decision of facilities improvement action. The container terminal operation model is constructed by accounting the variation of demand and facilities performance. In addition, for illustrating the conflicting issue that practically raises in the terminal operation, the model also takes into account the possible increment delay of facilities due to the increasing number of equipment, especially the container truck. Those variations expectantly reflect the uncertainty issue in the container terminal operation. A Monte Carlo simulation is invoked to propagate the variations by following the observed distribution. The problem is constructed within the framework of the combinatorial optimization problem for investigating the optimal decision of facilities improvement. A new variant of glow-worm swarm optimization (GSO) is thus proposed for solving the optimization, which is rarely explored in the transportation field. The model applicability is tested by considering the actual characteristics of the container terminal.

  9. Seismic design considerations of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    2001-10-01

    An Advisory Group Meeting (AGM) on Seismic Technologies of Nuclear Fuel Cycle Facilities was convened in Vienna from 12 to 14 November 1997. The main objective of the meeting was the investigation of the present status of seismic technologies in nuclear fuel cycle facilities in Member States as a starting point for understanding of the most important directions and trends of national initiatives, including research and development, in the area of seismic safety. The AGM gave priority to the establishment of a consistent programme for seismic assessment of nuclear fuel cycle facilities worldwide. A consultants meeting subsequently met in Vienna from 16 to 19 March 1999. At this meeting the necessity of a dedicated programme was further supported and a technical background to the initiative was provided. This publication provides recommendations both for the seismic design of new plants and for re-evaluation projects of nuclear fuel cycle facilities. After a short introduction of the general IAEA approach, some key contributions from Member State participants are presented. Each of them was indexed separately

  10. DESIGN AND THERMAL PERFORMANCE OF THE SOLAR BIOMASS HYBRID DRYER FOR CASHEW DRYING

    Directory of Open Access Journals (Sweden)

    Saravanan Dhanuskodi

    2014-12-01

    Full Text Available Drying of Cashew nut to remove testa is one of the most energy-intensive processes of cashew nut process industry. For this reason a hybrid dryer consisting of a solar flat plate collector, a biomass heater and a drying chamber is designed and fabricated. 40 kg of Cashew nut with initial moisture of 9 % is used in the experiment. The performance test of the dryer is carried out in two modes of operation: hybrid-forced convection and hybrid-natural convection. Drying time and drying efficiency during these two modes of operation are estimated and compared with the sun drying. The system is capable of attaining drying temperature between 50º and 70ºC. In the hybrid forced drying, the required moisture content of 3% is achieved within 7 hours and the average system efficiency is estimated as 5.08%. In the hybrid natural drying, the required moisture content is obtained in 9 hours and the average system efficiency is 3.17%. The fuel consumption during the drying process is 0.5 kg/hr and 0.75 kg/hr for forced mode and natural mode, respectively. The drying process in the hybrid forced mode of operation is twice faster than the sun drying. The dryer can be operated in any climatic conditions: as a solar dryer on normal sunny days, as a biomass dryer at night time and as a hybrid dryer on cloudy days. Based on the experimental study, it is concluded that the developed hybrid dryer is suitable for small scale cashew nut farmers in rural areas of developing countries.

  11. Optimization Of Freeze-Dried Starter For Yogurt By Full Factorial Experimental Design

    Directory of Open Access Journals (Sweden)

    Chen He

    2015-12-01

    Full Text Available With the rapidly development of fermented milk product, it is significant for enhancing the performance of starter culture. This paper not only investigated the influence of anti-freeze factors and freeze-drying protective agents on viable count, freeze-drying survival rate and yield of Lactobacillus bulgaricus (LB and Streptococcus thermophilus (ST, but also optimized the bacteria proportion of freeze-dried starter culture for yogurt by full factorial experimental design. The results showed as following: the freeze-drying protective agents or anti-freeze factors could enhanced survival rate of LB and ST; the freeze-dried LB and ST powders containing both of anti-freeze factors and freeze-drying protective agents had higher viable count and freeze-drying survival rate that were 84.7% and 79.7% respectively; In terms of fermentation performance, the best group of freeze-dried starter for yogurt was the compound of LB3 and ST2.

  12. Design study of an ERL Test Facility at CERN

    CERN Document Server

    Jensen, E; Brüning, O; Calaga, R; Catalan-Lasheras, N; Goddard, B; Klein, M; Torres-Sanchez, R; Valloni, A

    2014-01-01

    The modern concept of an Energy Recovery Linac allows providing large electron currents at large beam energy with low power consumption. This concept is used in FEL’s, electron-ion colliders and electron coolers. CERN has started a Design Study of an ERL Test Facility with the purpose of 1) studying the ERL principle, its specific beam dynamics and operational issues, as relevant for LHeC, 2) providing a test bed for superconducting cavity modules, cryogenics and integration, 3) studying beam induced quenches in superconducting magnets and protection methods, 4) providing test beams for detector R&D and other applications. It will be complementary to existing or planned facilities and is fostering international collaboration. The operating frequency of 802 MHz was chosen for performance and for optimum synergy with SPS and LHC; the design of the cryomodule has started. The ERL Test Facility can be constructed in stages from initially 150 MeV to ultimately 1 GeV in 3 passes, with beam currents of up to 8...

  13. Preliminary design of a Tandem-Mirror-Next-Step facility

    International Nuclear Information System (INIS)

    Damm, C.C.; Doggett, J.N.; Bulmer, R.H.

    1980-01-01

    The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m 3 , with a resultant neutron wall loading of 0.5 MW/m 2 . Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-yang magnets to provide magnetohydrodynamic (MHD) stability and thermal-barrier cells to help achieve a plasma Q of 4.7 (where Q = fusion power/injected power). Neutral beams at energies up to 200 keV are used for plasma heating, fueling, and barrier pumping. Electron cyclotron resonant heating at 50 and 100 GHz is used to control the electron temperature in the barriers. Based on the resulting engineering design, the overall cost of the facility is estimated to be just under $1 billion. Unresolved physics issues include central-cell β-limits against MHD ballooning modes (the assumed reference value of β exceeds the current theory-derived limit), and the removal of thermalized α-particles from the plasma

  14. Understanding facilities design parameters for a remanufacturing system

    Science.gov (United States)

    Topcu, Aysegul; Cullinane, Thomas

    2005-11-01

    Remanufacturing is rapidly becoming a very important element in the economies of the world. Products such as washing machines, clothes driers, automobile parts, cell phones and a wide range of consumer durable goods are being reclaimed and sent through processes that restore these products to levels of operating performance that are as good or better than their new product performance. The operations involved in the remanufacturing process add several new dimensions to the work that must be performed. Disassembly is an operation that rarely appears on the operations chart of a typical production facility. The inspection and test functions in remanufacturing most often involve several more tasks than those involved in the first time manufacturing cycle. A close evaluation of most any remanufacturing operation reveals several points in the process in which parts must be cleaned, tested and stored. Although several researchers have focused their work on optimizing the disassembly function and the inspection, test and store functions, very little research has been devoted to studying the impact of the facilities design on the effectiveness of the remanufacturing process. The purpose of this paper will be to delineate the differences between first time manufacturing operations and remanufacturing operations for durable goods and to identify the features of the facilities design that must be considered if the remanufacturing operations are to be effective.

  15. A Supply Chain Design Problem Integrated Facility Unavailabilities Management

    Directory of Open Access Journals (Sweden)

    Fouad Maliki

    2016-08-01

    Full Text Available A supply chain is a set of facilities connected together in order to provide products to customers. The supply chain is subject to random failures caused by different factors which cause the unavailability of some sites. Given the current economic context, the management of these unavailabilities is becoming a strategic choice to ensure the desired reliability and availability levels of the different supply chain facilities. In this work, we treat two problems related to the field of supply chain, namely the design and unavailabilities management of logistics facilities. Specifically, we consider a stochastic distribution network with consideration of suppliers' selection, distribution centres location (DCs decisions and DCs’ unavailabilities management. Two resolution approaches are proposed. The first approach called non-integrated consists on define the optimal supply chain structure using an optimization approach based on genetic algorithms (GA, then to simulate the supply chain performance with the presence of DCs failures. The second approach called integrated approach is to consider the design of the supply chain problem and unavailabilities management of DCs in the same model. Note that, we replace each unavailable DC by performing a reallocation using GA in the two approaches. The obtained results of the two approaches are detailed and compared showing their effectiveness.

  16. Database design for Physical Access Control System for nuclear facilities

    International Nuclear Information System (INIS)

    Sathishkumar, T.; Rao, G. Prabhakara; Arumugam, P.

    2016-01-01

    Highlights: • Database design needs to be optimized and highly efficient for real time operation. • It requires a many-to-many mapping between Employee table and Doors table. • This mapping typically contain thousands of records and redundant data. • Proposed novel database design reduces the redundancy and provides abstraction. • This design is incorporated with the access control system developed in-house. - Abstract: A (Radio Frequency IDentification) RFID cum Biometric based two level Access Control System (ACS) was designed and developed for providing access to vital areas of nuclear facilities. The system has got both hardware [Access controller] and software components [server application, the database and the web client software]. The database design proposed, enables grouping of the employees based on the hierarchy of the organization and the grouping of the doors based on Access Zones (AZ). This design also illustrates the mapping between the Employee Groups (EG) and AZ. By following this approach in database design, a higher level view can be presented to the system administrator abstracting the inner details of the individual entities and doors. This paper describes the novel approach carried out in designing the database of the ACS.

  17. Database design for Physical Access Control System for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sathishkumar, T., E-mail: satishkumart@igcar.gov.in; Rao, G. Prabhakara, E-mail: prg@igcar.gov.in; Arumugam, P., E-mail: aarmu@igcar.gov.in

    2016-08-15

    Highlights: • Database design needs to be optimized and highly efficient for real time operation. • It requires a many-to-many mapping between Employee table and Doors table. • This mapping typically contain thousands of records and redundant data. • Proposed novel database design reduces the redundancy and provides abstraction. • This design is incorporated with the access control system developed in-house. - Abstract: A (Radio Frequency IDentification) RFID cum Biometric based two level Access Control System (ACS) was designed and developed for providing access to vital areas of nuclear facilities. The system has got both hardware [Access controller] and software components [server application, the database and the web client software]. The database design proposed, enables grouping of the employees based on the hierarchy of the organization and the grouping of the doors based on Access Zones (AZ). This design also illustrates the mapping between the Employee Groups (EG) and AZ. By following this approach in database design, a higher level view can be presented to the system administrator abstracting the inner details of the individual entities and doors. This paper describes the novel approach carried out in designing the database of the ACS.

  18. BEAM LINE DESIGN FOR THE CERN HIRADMAT TEST FACILITY

    CERN Document Server

    Hessler, C; Goddard, B; Meddahi, M; Weterings, W

    2009-01-01

    The LHC phase II collimation project requires beam shock and impact tests of materials used for beam intercepting devices. Similar tests are also of great interest for other accelerator components such as beam entrance/exit windows and protection devices. For this purpose a dedicated High Radiation Material test facility (HiRadMat) is under study. This facility may be installed at CERN at the location of a former beam line. This paper describes the associated beam line which is foreseen to deliver a 450 GeV proton beam from the SPS with an intensity of up to 3×1013 protons per shot. Different beam line designs will be compared and the choice of the beam steering and diagnostic elements will be discussed, as well as operational issues.

  19. Beam Line Design for the CERN Hiradmat Test Facility

    CERN Document Server

    Hessler, C; Goddard, B; Meddahi, M; Weterings, W

    2010-01-01

    The LHC phase II collimation project requires beam shock and impact tests of materials used for beam intercepting devices. Similar tests are also of great interest for other accelerator components such as beam entrance/exit windows and protection devices. For this purpose a dedicated High Radiation Material test facility (HiRadMat) is under study. This facility may be installed at CERN at the location of a former beam line. This paper describes the associated beam line which is foreseen to deliver a 450 GeV proton beam from the SPS with an intensity of up to 3×10**13 protons per shot. Different beam line designs will be compared and the choice of the beam steering and diagnostic elements will be discussed, as well as operational issues.

  20. FPL design for lumber dry kiln using solar/wood energy in tropical latitudes

    Science.gov (United States)

    J. L. Tschernitz; W. T. Simpson

    1985-01-01

    Developing countries with a timber resource that can be manufactured into finished products either for local use or export often lack the capital to build high-cost dry kilns. Many of these countries are in the tropics where solar radiation and ambient temperatures are high. The low-cost solar/wood energy lumber dry kiln described in this report was designed and tested...

  1. Rational Design and Enhanced Biocompatibility of a Dry Adhesive Medical Skin Patch

    KAUST Repository

    Kwak, Moon Kyu

    2011-07-28

    A new type of medical skin patch is developed that contains high-density, mushroom-like micropillars. Such dry-adhesive micropillars are highly biocompatible, have minimized side effects, and provide reasonable normal adhesion strength. To arrive at optimal conditions for the dry adhesive skin patch, the proper design of various structural and material parameters of micropillars is investigated. Copyright © 2011 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  2. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, S. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  3. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, Stephanie Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  4. The International Space University's variable gravity research facility design

    Science.gov (United States)

    Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

    1991-09-01

    A manned mission to Mars will require long travel times between Earth and Mars. However, exposure to long-duration zero gravity is known to be harmful to the human body. Some of the harmful effects are loss of heart and lung capacity, inability to stand upright, muscular weakness and loss of bone calcium. A variable gravity research facility (VGRF) that would be placed in low Earth orbit (LEO) was designed by students of the International Space University 1989 Summer Session held in Strasbourg, France, to provide a testbed for conducting experiments in the life and physical sciences in preparation for a mission to Mars. This design exercise was unique because it addressed all aspects concerning a large space project. The VGRF design was described which was developed by international participants specializing in the following areas: the politics of international cooperation, engineering, architecture, in-space physiology, material and life science experimentation, data communications, business, and management.

  5. Magnet Design Considerations for Fusion Nuclear Science Facility

    Energy Technology Data Exchange (ETDEWEB)

    Zhai, Y. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Kessel, C. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); El-Guebaly, L. [Univ. of Wisconsin, Madison, WI (United States) Fusion Technology Institute; Titus, P. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

    2016-06-01

    The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility that provides a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between the International Thermonuclear Experimental Reactor (ITER) and the demonstration power plant (DEMO). Compared with ITER, the FNSF is smaller in size but generates much higher magnetic field, i.e., 30 times higher neutron fluence with three orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center with a plasma major radius of 4.8 m and a minor radius of 1.2 m and a peak field of 15.5 T on the toroidal field (TF) coils for the FNSF. Both low-temperature superconductors (LTS) and high-temperature superconductors (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high-performance ternary restacked-rod process Nb3Sn strands for TF magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high-aspect-ratio rectangular CICC design are evaluated for FNSF magnets, but low-activation-jacket materials may need to be selected. The conductor design concept and TF coil winding pack composition and dimension based on the horizontal maintenance schemes are discussed. Neutron radiation limits for the LTS and HTS superconductors and electrical insulation materials are also reviewed based on the available materials previously tested. The material radiation limits for FNSF magnets are defined as part of the conceptual design studies for FNSF magnets.

  6. Design Lessons Drawn from the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2011-05-01

    This report provides an updated compilation incorporating the most recent lessons learned from decommissioning and remediation projects. It is intended as a 'road map' to those seeking to apply these lessons. The report presents the issues in a concise and systematic manner, along with practical, thought-provoking examples. The most important lessons learned in recent years are organized and examined to enable the intended audience to gauge the importance of this aspect of the planning for new nuclear facilities. These will be of special interest to those seeking to construct nuclear facilities for the first time. In Sections 1 and 2, the current situation in the field of decommissioning is reviewed and the relevance and importance of beneficial design features is introduced. A more detailed review of previous and current lessons learned from decommissioning is given in Section 3 where different aspects of the decommissioning process are analysed. From this analysis beneficial design features have been extracted and identified in Section 4 which includes two comprehensive tables where brief descriptions of the features are summarized and responsibilities are identified. Conclusions and key design features and key recommendations are given in Section 5. Two Annexes are included to provide lessons from past projects and past experience and to record notes and extracts taken from a comprehensive list of publications listed in the References on page 47.

  7. 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

  8. Shield design for the Fusion Materials Irradiation Test facility

    International Nuclear Information System (INIS)

    Carter, L.L.; Mann, F.M.; Morford, R.J.; Wilcox, A.D.; Johnson, D.L.; Huang, S.T.

    1983-03-01

    The shield design for the Fusion Materials Irradiation Test facility is based upon one-, two- and three-dimensional transport calculations with experimental measurements utilized to refine the nuclear data including the neutron cross sections from 20 to 50 MeV and the gamma ray and neutron source terms. The high energy neutrons and deuterons produce activation products from the numerous reactions that are kinematically allowed. The analyses for both beam-on and beam-off (from the activation products) conditions have required extensive nuclear data libraries and the utilization of Monte Carlo, discrete ordinates, point kernel and auxiliary computer codes

  9. Seismic design criteria of fire protection systems for DOE facilities

    International Nuclear Information System (INIS)

    Hardy, G.; Cushing, R.; Driesen, G.

    1991-01-01

    Fire protection systems are critical to the safety of personnel and to the protection of inventory during any kind of emergency situation that involves a fire. The importance of these fire protection systems is hightened for DOE facilities which often house nuclear, chemical or scientific processes. Current research into the topic of open-quotes fires following earthquakesclose quotes has demonstrated that the risks of a fire starting as a result of a major earthquake can be significant. Thus, fire protection systems need to be designed to withstand the anticipated seismic event for the site in question

  10. Probabilistic Assessment Method of Turbojet Engine Impact on an Interim Dry Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Almomania, Belal; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of); Lee, Sang Hoon [Keimyung University, Daegu (Korea, Republic of)

    2016-05-15

    This paper describes an analytical method of structural analysis for an interim storage facility subjected to aircraft jet engine based on a probabilistic approach. This method will be employed in the process of aircraft risk model for the interim storage facilities. The analytical formulation of the engine impact and the perforation to find the required thickness of concrete to protect the equipment inside the structure is an enormously complex impact phenomenon. Therefore, all the available formulas describing perforation phenomena are empirical and based on experimental data. In this paper, a method with sample results to determine the local failure probability of the facility's wall and the probable residual velocities after passed through the target by applying a probabilistic approach was proposed. Normal engine impact on the wall shield using applicable empirical formulas provides a best estimation of perforation depth and residual velocity with intent of producing conservative outcomes.

  11. Conceptual design of interim storage facility for CNAI

    International Nuclear Information System (INIS)

    Fuenzalida Troyano, Carlos S.; Bergallo, Juan E.; Nassini, Horacio E.P.; Blanco, Anibal; Delmastro, Dario F.

    2007-01-01

    The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author) [es

  12. Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

    International Nuclear Information System (INIS)

    Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

    2010-01-01

    Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

  13. Design Improvements and ALARA at U.S. Uranium In Situ Recovery Facilities - 16415

    International Nuclear Information System (INIS)

    Brown, S.H.

    2009-01-01

    In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed . Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium In Situ Leaching / In Situ Recovery (ISL / ISR - also referred to as 'solution mining'), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and are expected to make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since the mid 1970's. However, current designs are expected to result in less radiological wastes and emissions relative to these 'first' generation plants (which were designed, constructed and operated through the 1980's). These early designs typically used alkaline leach chemistries in situ including use of ammonium carbonate which resulted in groundwater restoration challenges, open to air recovery vessels and high temperature calcining systems for final product drying vs the 'zero emission' vacuum dryers as typically used today. Improved containment, automation and instrumentation control and use of vacuum dryers in the design of current generation plants are expected to reduce production of secondary waste byproduct material, reduce Radon emissions and reduce potential for employee exposure to uranium concentrate aerosols at the back end of the milling process. In Situ Recovery in the U.S. typically involves the circulation of groundwater, fortified with oxidizing (gaseous oxygen e.g) and complexing agents (carbon

  14. Evaluation of Pathogen Removal in a Solar Sludge Drying Facility Using Microbial Indicators

    Directory of Open Access Journals (Sweden)

    D. İpek Kurtböke

    2010-02-01

    Full Text Available South East Queensland is one of the fastest growing regions in Australia with a correspondingly rapid increase in sewage production. In response, local councils are investing in more effective and sustainable options for the treatment and reuse of domestic and industrial effluents. A novel, evaporative solar dryer system has been installed on the Sunshine Coast to convert sewage sludge into a drier, usable form of biosolids through solar radiation exposure resulting in decreased moisture concentration and pathogen reduction. Solar-dried biosolids were analyzed for selected pathogenic microbial, metal and organic contaminants at the end of different drying cycles in a collaborative study conducted with the Regional Council. Although fecal coliforms were found to be present, enteroviruses, parasites, E. coli, and Salmonella sp. were not detected in the final product. However, elevated levels of zinc and copper were still present which restricted public use of the biosolids. Dilution of the dried biosolids with green waste as well as composting of the biosolids is likely to lead to the production of an environmentally safe, Class A end-product.

  15. Evaluation of pathogen removal in a solar sludge drying facility using microbial indicators.

    Science.gov (United States)

    Shanahan, Emily F; Roiko, Anne; Tindale, Neil W; Thomas, Michael P; Walpole, Ronald; Kurtböke, D Ipek

    2010-02-01

    South East Queensland is one of the fastest growing regions in Australia with a correspondingly rapid increase in sewage production. In response, local councils are investing in more effective and sustainable options for the treatment and reuse of domestic and industrial effluents. A novel, evaporative solar dryer system has been installed on the Sunshine Coast to convert sewage sludge into a drier, usable form of biosolids through solar radiation exposure resulting in decreased moisture concentration and pathogen reduction. Solar-dried biosolids were analyzed for selected pathogenic microbial, metal and organic contaminants at the end of different drying cycles in a collaborative study conducted with the Regional Council. Although fecal coliforms were found to be present, enteroviruses, parasites, E. coli, and Salmonella sp. were not detected in the final product. However, elevated levels of zinc and copper were still present which restricted public use of the biosolids. Dilution of the dried biosolids with green waste as well as composting of the biosolids is likely to lead to the production of an environmentally safe, Class A end-product.

  16. Design and physicochemical characterization of advanced spray-dried tacrolimus multifunctional particles for inhalation.

    Science.gov (United States)

    Wu, Xiao; Hayes, Don; Zwischenberger, Joseph B; Kuhn, Robert J; Mansour, Heidi M

    2013-01-01

    The aim of this study was to design, develop, and optimize respirable tacrolimus microparticles and nanoparticles and multifunctional tacrolimus lung surfactant mimic particles for targeted dry powder inhalation delivery as a pulmonary nanomedicine. Particles were rationally designed and produced at different pump rates by advanced spray-drying particle engineering design from organic solution in closed mode. In addition, multifunctional tacrolimus lung surfactant mimic dry powder particles were prepared by co-dissolving tacrolimus and lung surfactant mimic phospholipids in methanol, followed by advanced co-spray-drying particle engineering design technology in closed mode. The lung surfactant mimic phospholipids were 1,2-dipalmitoyl-sn-glycero-3-phosphocholine and 1,2-dipalmitoyl-sn-glycero-3-[phosphor-rac-1-glycerol]. Laser diffraction particle sizing indicated that the particle size distributions were suitable for pulmonary delivery, whereas scanning electron microscopy imaging indicated that these particles had both optimal particle morphology and surface morphology. Increasing the pump rate percent of tacrolimus solution resulted in a larger particle size. X-ray powder diffraction patterns and differential scanning calorimetry thermograms indicated that spray drying produced particles with higher amounts of amorphous phase. X-ray powder diffraction and differential scanning calorimetry also confirmed the preservation of the phospholipid bilayer structure in the solid state for all engineered respirable particles. Furthermore, it was observed in hot-stage micrographs that raw tacrolimus displayed a liquid crystal transition following the main phase transition, which is consistent with its interfacial properties. Water vapor uptake and lyotropic phase transitions in the solid state at varying levels of relative humidity were determined by gravimetric vapor sorption technique. Water content in the various powders was very low and well within the levels necessary

  17. Safety analysis report for the cold vacuum drying facility, phase 2, supporting installation of process systems

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1998-01-01

    SNF Project emergencies span the spectrum of identified emergencies for SNF Project facilities, from worker injury to general emergencies with potential public impact. Facility events include fire and/or explosion, radioactive material release, chlorine gas release, hazardous material release, loss of water in the fuel basins, and loss of electrical power. Natural events include seismic events, high winds, range fires, flooding, lightning strikes, tornado, and an aircraft crash. Security contingencies include bomb threat and/or explosive device, sabotage, and hostage situation and/or armed intruder as described in DOE/RL-94-02 (DOE 1997 b). This Chapter 15.0 applies to all operations, facilities, and personnel, including subcontractors, vendors, visitors, and any non-contractor tenants in SNF Project-controlled facilities. The EPP addresses both individual and organizational graded responses to the spectrum of emergencies, which includes hypothetical accidents with very low occurrence frequencies. The planning, accomplished in the EPP and the BEPs, provides the response actions for these emergencies. This chapter links the SNF Project EPP to DOE/RL-94-02 (DOE 1997 b), which provides the link to subsequent state and local off site EPPs. Integration of these programs links potential onsite events with onsite and offsite impacts. This integration assists in mitigation and recovery and provides for protection of the health and safety of the workers, the public, and the environment

  18. Beam generation at next generation RIB facilities: conceptual design studies

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Y.; Alton, G.D. [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2004-12-27

    In order to produce useful intensities of radioactive ion beams, ISOL targets must be designed that can withstand direct irradiation with high power beams. Computational thermal modeling techniques offer a cost effective way for evaluating prototype target concepts in the quest to find an optimum design. In this report, a number of codes are utilized to select target materials and to model the primary beam power density, thermal transport and temperature distributions in ISOL targets. These studies suggest that radiation cooling, in combination with Lissajous beam scan techniques, can be used to control temperatures in practically sized targets, to levels commensurate with irradiation with 1-GeV, 400-kW proton beams for next generation RIB facilities.

  19. 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.

  20. CEBAF [Continuous Electron Beam Accelerator Facility] design report

    International Nuclear Information System (INIS)

    1986-05-01

    This book describes the conceptual design of, and the planning for, the Continuous Electron Beam Accelerator Facility (CEBAF), which will be a high-intensity, continuous-wave electron linear accelerator (linac) for nuclear physics. Its principal scientific goal is to understand the quark structure, behavior, and clustering of individual nucleons in the nuclear medium, and simultaneously to understand the forces governing this behavior. The linac will consist of 1 GeV of accelerating structure, split into two antiparallel 0.5-GeV segments. The segments will be connected by a beam transport system to circulate the electron beams from one segment to the other for up to four complete passes of acceleration. The maximum beam energy will be 4 GeV at a design current of 200 microamperes. The accelerator complex will also include systems to extract three continuous beams from the linac and to deliver them to three experimental halls equipped with detectors and instrumentation for nuclear physics research. The accelerating structure will be kept superconducting within insulated cryostats filled with liquid helium produced at a central helium refrigerator and distributed to the cryostats via insulated transfer lines. An injector, instrumentation and controls for the accelerator, radio-frequency power systems, and several support facilities will also be provided. A cost estimate based on the Work Breakdown Structure has been completed. Assuming a five-year construction schedule starting early in FY 1987, the total estimated cost is $236 million (actual year dollars), including contingency

  1. 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

  2. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities; Instalaciones de almacenamiento de combustible nuclear gastado en seco para instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  3. Uncertainty analysis as essential step in the establishment of the dynamic Design Space of primary drying during freeze-drying

    DEFF Research Database (Denmark)

    Mortier, Severine Therese F. C.; Van Bockstal, Pieter-Jan; Corver, Jos

    2016-01-01

    Large molecules, such as biopharmaceuticals, are considered the key driver of growth for the pharmaceutical industry. Freeze-drying is the preferred way to stabilise these products when needed. However, it is an expensive, inefficient, time- and energy-consuming process. During freeze-drying...... for pharmaceutical freeze-drying. Traditionally, the chamber pressure and shelf temperature are kept constant during primary drying, leading to less optimal process conditions. In this paper it is demonstrated how a mechanistic model of the primary drying step gives the opportunity to determine the optimal dynamic...

  4. Conceptual design of an in-space cryogenic fluid management facility, executive summary

    Science.gov (United States)

    Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

    1981-01-01

    The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is summarized. The preliminary facility definition, conceptual design and design analysis, and facility development plan, including schedule and cost estimates for the facility, are presented.

  5. Dry sorbent injection of trona to control acid gases from a pilot-scale coal-fired combustion facility

    Directory of Open Access Journals (Sweden)

    Tiffany L. B. Yelverton

    2016-01-01

    Full Text Available  Gaseous and particulate emissions from the combustion of coal have been associated with adverse effects on human and environmental health, and have for that reason been subject to regulation by federal and state governments. Recent regulations by the United States Environmental Protection Agency have further restricted the emissions of acid gases from electricity generating facilities and other industrial facilities, and upcoming deadlines are forcing industry to consider both pre- and post-combustion controls to maintain compliance. As a result of these recent regulations, dry sorbent injection of trona to remove acid gas emissions (e.g. HCl, SO2, and NOx from coal combustion, specifically 90% removal of HCl, was the focus of the current investigation. Along with the measurement of HCl, SO2, and NOx, measurements of particulate matter (PM, elemental (EC, and organic carbon (OC were also accomplished on a pilot-scale coal-fired combustion facility. Gaseous and particulate emissions from a coal-fired combustor burning bituminous coal and using dry sorbent injection were the focus of the current study. From this investigation it was shown that high levels of trona were needed to achieve the goal of 90% HCl removal, but with this increased level of trona injection the ESP and BH were still able to achieve greater than 95% fine PM control. In addition to emissions reported, measurement of acid gases by standard EPA methods were compared to those of an infrared multi-component gas analyzer. This comparison revealed good correlation for emissions of HCl and SO2, but poor correlation in the measurement of NOx emissions.

  6. Quality by design approach in the optimization of the spray-drying process.

    Science.gov (United States)

    Baldinger, Arnaud; Clerdent, Lucas; Rantanen, Jukka; Yang, Mingshi; Grohganz, Holger

    2012-01-01

    The aim of this study was to illustrate the influence of the processing parameters, inlet temperature, atomization air flow rate and feed flow rate, on critical quality attributes of spray-dried powders using design of experiments (DoE). Spray-dried powders were characterized by laser diffraction, X-ray powder diffraction (XRPD) and near-infrared spectroscopy (NIR). Multivariate analysis of two different experimental designs was performed to elucidate the optimal process conditions. XRPD revealed that the spray-dried powders consisted of crystalline β-mannitol and amorphous trehalose. Non-invasive NIR measurement was successfully used for correlating the critical quality attribute particle size with size determined by laser diffraction. The full factorial design proved to be unsuitable due to the non-linear influence of factors. The composite face-centered design improved the quality of the models and showed both linear and non-linear influence of the parameters on the outcomes. A model explaining the influence of the factors on all quality attributes showed similar results as the models optimized for a single response. This study showed the applicability of DoE for the investigation of spray-dried powders. The knowledge of the interplay between process parameters and quality attributes will enable rational process design to achieve a desired outcome.

  7. Particle Engineering Via Mechanical Dry Coating in the Design of Pharmaceutical Solid Dosage Forms.

    Science.gov (United States)

    Qu, Li; Morton, David A V; Zhou, Qi Tony

    2015-01-01

    Cohesive powders are problematic in the manufacturing of pharmaceutical solid dosage forms because they exhibit poor flowability, fluidization and aerosolization. These undesirable bulk properties of cohesive powders represent a fundamental challenge in the design of efficient pharmaceutical manufacturing processes. Recently, mechanical dry coating has attracted increasing attention as it can improve the bulk properties of cohesive powders in a cheaper, simpler, safer and more environment-friendly way than the existing solvent-based counterparts. In this review, mechanical dry coating techniques are outlined and their potential applications in formulation and manufacturing of pharmaceutical solid dosage forms are discussed. Reported data from the literature have shown that mechanical dry coating holds promise for the design of superior pharmaceutical solid formulations or manufacturing processes by engineering the interfaces of cohesive powders in an efficient and economical way.

  8. Design and operation of radioactive waste incineration facilities

    International Nuclear Information System (INIS)

    1992-01-01

    The purpose of this guide is to provide safety guidance for the design and operation of radioactive waste incineration facilities. The guide emphasizes the design objectives and system requirements to be met and provides recommendations for the procedure of process selection and equipment design and operation. It is recognized that some incinerators may handle only very low or 'insignificant' levels of radioactivity, and in such cases some requirements or recommendations of this guide may not fully apply. Nevertheless, it is expected that any non-compliance with the guide will be addressed and justified in the licensing process. It is also recognized that the regulatory body may place a limit on the level of the radioactivity of the waste to be incinerated at a specific installation. For the purpose of this guide an insignificant level of release of radioactivity may typically be defined as either the continuous or single event release of the design basis radionuclide inventory that represents a negligible risk to the population, the operating personnel, and/or the environment. The guidance on what constitutes a negligible risk and how to translate negligible risk or dose into level of activity can be found in Safety Series No. 89, IAEA, Vienna. 20 refs, 1 fig

  9. RF structure design of the China Material Irradiation Facility RFQ

    Science.gov (United States)

    Li, Chenxing; He, Yuan; Xu, Xianbo; Zhang, Zhouli; Wang, Fengfeng; Dou, Weiping; Wang, Zhijun; Wang, Tieshan

    2017-10-01

    The radio frequency structure design of the radio frequency quadrupole (RFQ) for the front end of China Material Irradiation Facility (CMIF), which is an accelerator based neutron irradiation facility for fusion reactor material qualification, has been completed. The RFQ is specified to accelerate 10 mA continuous deuteron beams from the energies of 20 keV/u to 1.5 MeV/u within the vane length of 5250 mm. The working frequency of the RFQ is selected to 162.5 MHz and the inter-vane voltage is set to 65 kV. Four-vane cavity type is selected and the cavity structure is designed drawing on the experience of China Initiative Accelerator Driven System (CIADS) Injector II RFQ. In order to reduce the azimuthal asymmetry of the field caused from errors in fabrication and assembly, a frequency separation between the working mode and its nearest dipole mode is reached to 17.66 MHz by utilizing 20 pairs of π-mode stabilizing loops (PISLs) distributed along the longitudinal direction with equal intervals. For the purpose of tuning, 100 slug tuners were introduced to compensate the errors caused by machining and assembly. In order to obtain a homogeneous electrical field distribution along cavity, vane cutbacks are introduced and output endplate is modified. Multi-physics study of the cavity with radio frequency power and water cooling is performed to obtain the water temperature tuning coefficients. Through comparing to the worldwide CW RFQs, it is indicated that the power density of the designed structure is moderate for operation under continuous wave (CW) mode.

  10. Towards the implementation of e-manufacturing: design of an automatic tea drying control system

    Directory of Open Access Journals (Sweden)

    Mabvuu, Never

    2014-11-01

    Full Text Available Many of the production costs for producing tea are attributable to the process of drying the tea. E-manufacturing can assist companies to reduce these production costs by making crucial information available to decision-makers so that they can make informed decisions. This paper presents an application of e-manufacturing to the design of an automatic tea drying control system. This control system will ensure that the multiple drying parameters such as temperature, dryer-exit tea moisture content, and fuel consumption are maintained at optimal states during the course of the drying of tea. The additional aim of this system is to balance the cost of production and the quality of the final product. Using the Guggenheim-Anderson-De Boer (GAB model, the optimum drying temperature was found to be 100-110°C, while maintaining a dryer-exit tea moisture content of 3 to 3.12 per cent, at a drying rate of 3 per cent per minute. A Barix control application to control the system’s activities, using the web user interface (WUI, was also developed.

  11. Criteria for designing an interim waste storage facility

    International Nuclear Information System (INIS)

    Vicente, Roberto

    2011-01-01

    The long-lived radioactive wastes with activity above clearance levels generated by radioisotope users in Brazil are collected into centralized waste storage facilities under overview of the National Commission on Nuclear Energy (CNEN). One of these centers is the Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, which since 1978 also manages the wastes generated by IPEN itself. Present inventory of stored wastes includes about 160 tons of treated wastes, distributed in 1290 steel, 200-liters drums, and 52 steel, 1.6 m 3 -boxes, with an estimated total activity of 0.8 TBq. Radionuclides present in these wastes are fission and activation products, transuranium elements, and isotopes from the uranium and thorium decay series. The capacity and quality of the storage rooms at GRR evolved along the last decades to meet the requirements set forth by the Brazilian regulatory authorities.From a mere outdoor concrete platform over which drums were simply stacked and covered with canvas to the present day building, a great progress was made in the storage method. In this paper we present the results of a study in the criteria that were meant to guide the design of the storage building, many of which were eventually adopted in the final concept, and are now built-in features of the facility. We also present some landmarks in the GRR's activities related to waste management in general and waste storage in particular, until the treated wastes of IPEN found their way into the recently licensed new storage facility. (author)

  12. Designing a model to minimize inequities in hemodialysis facilities distribution

    Directory of Open Access Journals (Sweden)

    Teresa M. Salgado

    2011-11-01

    Full Text Available Portugal has an uneven, city-centered bias in the distribution of hemodialysis centers found to contribute to health care inequities. A model has been developed with the aim of minimizing access inequity through the identification of the best possible localization of new hemodialysis facilities. The model was designed under the assumption that individuals from different geographic areas, ceteris paribus, present the same likelihood of requiring hemodialysis in the future. Distances to reach the closest hemodialysis facility were calculated for every municipality lacking one. Regions were scored by aggregating weights of the “individual burden”, defined as the burden for an individual living in a region lacking a hemodialysis center to reach one as often as needed, and the “population burden”, defined as the burden for the total population living in such a region. The model revealed that the average travelling distance for inhabitants in municipalities without a hemodialysis center is 32 km and that 145,551 inhabitants (1.5% live more than 60 min away from a hemodialysis center, while 1,393,770 (13.8% live 30-60 min away. Multivariate analysis showed that the current localization of hemodialysis facilities is associated with major urban areas. The model developed recommends 12 locations for establishing hemodialysis centers that would result in drastically reduced travel for 34 other municipalities, leaving only six (34,800 people with over 60 min of travel. The application of this model should facilitate the planning of future hemodialysis services as it takes into consideration the potential impact of travel time for individuals in need of dialysis, as well as the logistic arrangements required to transport all patients with end-stage renal disease. The model is applicable in any country and health care planners can opt to weigh these two elements differently in the model according to their priorities.

  13. A pilot scale electrical infrared dry-peeling system for tomatoes: design and performance evaluation

    Science.gov (United States)

    A pilot scale infrared dry-peeling system for tomatoes was designed and constructed. The system consisted of three major sections including the IR heating, vacuum, and pinch roller sections. The peeling performance of the system was examined under different operational conditions using tomatoes with...

  14. Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

    CERN Document Server

    Gencer, A.; Efthymiopoulos, I.; Yiğitoğlu, M.

    2016-01-01

    Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between View the MathML source10μA and View the MathML source1.2mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam ...

  15. Monitoring of dry anaerobic fermentation in experimental facility with use of biofilm reactor

    Directory of Open Access Journals (Sweden)

    Milan Šinkora

    2011-01-01

    Full Text Available Anaerobic fermentation is a process in which almost any organic mass may be transformed into an energetically rich biogas and a fermentation residue. Only strictly anaerobic microorganisms enter into the process; thus the process may take place only in a hermetically sealed environment. With regard to the world wide situation, where the increase in the proportion of energy from sustainable sources is in demand, anaerobic fermentation offers the possibility of transforming farm waste, farm products and municipality waste of biological character into electricity. This electricity may subsequently become an interesting source of income. The system may be proposed to agricultural companies as well as to municipality corporations. The process of fermentation may be carried out as dry fermentation or as liquid fermentation. Dry fermentation, working with materials where the percentage of dry matter exceeds 15 %, is the topic of this paper. This method has been frequently discussed as a method of processing organic material without waste water and thus the volume of material as well as the size of the biogas plant considerably decreases. To enable progress in the process, it is necessary to use a biologically active liquid solution containing the essential micro-organisms, often termed “percolate”. To activate a fresh substrate, fermented material adulterant containing cultivated microorganisms from previous processes is used; the ratio in which it is used is approximately one third to one fifth. “Percolate strategy” is another phrase used for sustaining the anaerobic fermentation; material is sprinkled on the percolate in the precisely defined cycles. In addition, the biologically active liquid solution contains organic substances washed out from the fermented material. With regard to its amount, this paper has become an impulse for the research in the amount of biogas which may be subsequently produced from the percolate in the so

  16. Designing an Institutional Web-based Core Facility Management System

    Science.gov (United States)

    Tabarini, D.; Clisham, S.; John, D.; Hagen, A.

    2011-01-01

    The authors and their four institutions collaborated to (i) identify the key challenges to core facility management; (ii) identify the requirements for an effective core facility management system; (iii) design, test and deploy such a system. Through a series of interviews with all participants in the core work flow (customers, core staff, administrators), the team identified a number of key challenges, including: (i) difficulty for researchers in identifying available services; (ii) inconsistent processes for requesting services; (iii) inadequate controls for approving service requests; (iv) inefficient processes for tracking and communicating about project processes; (v) time-consuming billing practices; (vi) incomplete revenue capture; (vii) manual reporting processes. The team identified the following requirements for a system to address these challenges: (i) ability to support a broad range of core business practices such as complex quote generation and project management; calendaring/equipment reservation management; sample tracking; complex forms; and import of usage data from hardware; (ii) ability to offer services for both internal and external customers, including flexible pricing and off-site access; (iii) ability to interact with institutional financial systems (e.g. SAP, PeopleSoft, Lawson, SunGard Banner) and identify management systems (e.g. Microsoft Active Directory, LDAP, and other SAML 2.0-compliant services). The team developed and deployed this system across the collaborative partners, as well as other major research institutions.

  17. Design of MagLIF experiments using the Z facility

    Science.gov (United States)

    Sefkow, Adam

    2013-10-01

    The MagLIF (Magnetized Liner Inertial Fusion) concept has been presented as a path toward obtaining substantial fusion yields using the Z facility, and related experiments have begun in earnest at Sandia National Laboratories. We present fully integrated numerical magnetohydrodynamic simulations of the MagLIF concept, which include laser preheating of the fuel, the presence of electrodes, and end loss effects. These simulations have been used to design neutron-producing integrated MagLIF experiments on the Z facility for the capabilities that presently exist, namely, D2 fuel, peak currents of Imax 15-18 MA, pre-seeded axial magnetic fields of Bz0 = 7-10 T, and laser preheat energies of Elaser = 2-3 kJ delivered in 2 ns. The first fully integrated experiments, based on these simulations, are planned to occur in 2013. Neutron yields in excess of 1011 are predicted with the available laser preheat energy and accelerator drive energy. In several years, we plan to upgrade the laser to increase Elaser = by several more kJ, provide Bz0 up to 30 T, deliver Imax 22 MA or more to the load, and develop the capability to use DT fuel. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

  18. Accelerator shield design of KIPT neutron source facility

    International Nuclear Information System (INIS)

    Zhong, Z.; Gohar, Y.

    2013-01-01

    Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the design development of a neutron source facility at KIPT utilizing an electron-accelerator-driven subcritical assembly. Electron beam power is 100 kW, using 100 MeV electrons. The facility is designed to perform basic and applied nuclear research, produce medical isotopes, and train young nuclear specialists. The biological shield of the accelerator building is designed to reduce the biological dose to less than 0.5-mrem/hr during operation. The main source of the biological dose is the photons and the neutrons generated by interactions of leaked electrons from the electron gun and accelerator sections with the surrounding concrete and accelerator materials. The Monte Carlo code MCNPX serves as the calculation tool for the shield design, due to its capability to transport electrons, photons, and neutrons coupled problems. The direct photon dose can be tallied by MCNPX calculation, starting with the leaked electrons. However, it is difficult to accurately tally the neutron dose directly from the leaked electrons. The neutron yield per electron from the interactions with the surrounding components is less than 0.01 neutron per electron. This causes difficulties for Monte Carlo analyses and consumes tremendous computation time for tallying with acceptable statistics the neutron dose outside the shield boundary. To avoid these difficulties, the SOURCE and TALLYX user subroutines of MCNPX were developed for the study. The generated neutrons are banked, together with all related parameters, for a subsequent MCNPX calculation to obtain the neutron and secondary photon doses. The weight windows variance reduction technique is utilized for both neutron and photon dose calculations. Two shielding materials, i.e., heavy concrete and ordinary concrete, were considered for the shield design. The main goal is to maintain the total

  19. Ventilation and exhaust ducts for dry storage facilities with self-heating radioactive materials

    International Nuclear Information System (INIS)

    Knappe, O.; Hame, W.

    1986-01-01

    The storage facilities are cooled by natural convection. In order to achieve this, the air inlet and outlet openings or ducts for the PWR and BWR fuel store are arranged at the level of the roof structure. There are two types of air inlet openings arranged on top and on the sides respectively but having got common inlet ducts. Air supply is improved by means of baffle noses, baffle edges, and baffle plates. The exhaust air ducts terminate near the roof structure, the openings having got dropping edges, protective sills and separating plates. (orig./PW)

  20. Safety issues relating to the design of fusion power facilities

    International Nuclear Information System (INIS)

    Stasko, R.R.; Wong, K.Y.; Russell, S.B.

    1986-06-01

    In order to make fusion power a viable future source of energy, it will be necessary to ensure that the cost of power for fusion electric generation is competitive with advanced fission concepts. In addition, fusion power will have to live up to its original promise of being a more radiologically benign technology than fission, and be able to demonstrate excellent operational safety performance. These two requirements are interrelated, since the selection of an appropriate safety philosophy early in the design phase could greatly reduce or eliminate the capital costs of elaborate safety related and protective sytems. This paper will briefly overview a few of the key safety issues presently recognized as critical to the ultimate achievement of licensable, environmentally safe and socially acceptable fusion power facilities. 12 refs

  1. Design and physicochemical characterization of advanced spray-dried tacrolimus multifunctional particles for inhalation

    Directory of Open Access Journals (Sweden)

    Wu X

    2013-02-01

    Full Text Available Xiao Wu,1 Don Hayes Jr,2,3 Joseph B Zwischenberger,4 Robert J Kuhn,5 Heidi M Mansour1,61University of Kentucky, College of Pharmacy, Department of Pharmaceutical Sciences-Drug Development Division, Lexington, KY, USA; 2The Ohio State University College of Medicine, Departments of Pediatrics and Internal Medicine, Lung and Heart-Lung Transplant Programs, Nationwide Children's Hospital, Columbus, OH, USA; 3The Ohio State University College of Medicine, The Davis Heart and Lung Research Institute, Columbus, OH, USA; 4University of Kentucky College of Medicine, Departments of Pediatrics, Biomedical Engineering, Diagnostic Radiology, and Surgery, Lexington, KY, USA; 5University of Kentucky, College of Pharmacy, Division of Pharmacy Practice and Science, Lexington, KY, USA; 6University of Kentucky, Center of Membrane Sciences, Lexington, KY, USAAbstract: The aim of this study was to design, develop, and optimize respirable tacrolimus microparticles and nanoparticles and multifunctional tacrolimus lung surfactant mimic particles for targeted dry powder inhalation delivery as a pulmonary nanomedicine. Particles were rationally designed and produced at different pump rates by advanced spray-drying particle engineering design from organic solution in closed mode. In addition, multifunctional tacrolimus lung surfactant mimic dry powder particles were prepared by co-dissolving tacrolimus and lung surfactant mimic phospholipids in methanol, followed by advanced co-spray-drying particle engineering design technology in closed mode. The lung surfactant mimic phospholipids were 1,2-dipalmitoyl-sn-glycero-3-phosphocholine and 1,2-dipalmitoyl-sn-glycero-3-[phosphor-rac-1-glycerol]. Laser diffraction particle sizing indicated that the particle size distributions were suitable for pulmonary delivery, whereas scanning electron microscopy imaging indicated that these particles had both optimal particle morphology and surface morphology. Increasing the pump rate

  2. Cost Optimal Design of a Single-Phase Dry Power Transformer

    Directory of Open Access Journals (Sweden)

    Raju Basak

    2015-08-01

    Full Text Available The Dry type transformers are preferred to their oil-immersed counterparts for various reasons, particularly because their operation is hazardless. The application of dry transformers was limited to small ratings in the earlier days. But now these are being used for considerably higher ratings.  Therefore, their cost-optimal design has gained importance. This paper deals with the design procedure for achieving cost optimal design of a dry type single-phase power transformer of small rating, subject to usual design constraints on efficiency and voltage regulation. The selling cost for the transformer has been taken as the objective function. Only two key variables have been chosen, the turns/volt and the height: width ratio of window, which affects the cost function to high degrees. Other variables have been chosen on the basis of designers’ experience. Copper has been used as conductor material and CRGOS as core material to achieve higher efficiency, lower running cost and compact design. The electrical and magnetic loadings have been kept at their maximum values without violating the design constraints. The optimal solution has been obtained by the method of exhaustive search using nested loops.

  3. Technology transfer and design conversion of a dry spent fuel storage system in Ukraine

    International Nuclear Information System (INIS)

    Peacock, R.C.; Marcelli, D.G.

    1998-01-01

    A number of unique issues surfaced in the technology transfer and design conversion of a US dry spent fuel storage technology in Ukraine. Unique challenges were encountered in the areas of nuclear design conversion, technical codes and standards, material selection and qualification, fabrication, construction and testing, quality assurance, documentation, and translation and verification processes. Technology transfer and design conversion were undertaken for both concrete and steel components for the project. The overall effort presented significant technical and cultural challenges to both the US and Ukrainian side, but technical exchange and design improvements to achieve a common goal have been reached. (author)

  4. 40 CFR 60.40 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Applicability and designation of affected facility. 60.40 Section 60.40 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED....40 Applicability and designation of affected facility. (a) The affected facilities to which the...

  5. Screening freeze-drying cryoprotectants for Saccharomyces boulardii by Plackett-Burman design

    Directory of Open Access Journals (Sweden)

    He CHEN

    2016-12-01

    Full Text Available As a lyophilized product, Saccharomyces boulardii has been commonly used to treat diarrhea in adults. However, there are few studies focusing on the preparation of its freeze-drying powder. This paper investigated the effect of lyoprotectants on the freeze-drying survival rate and the number of viable cells for vacuum freezedried powder of S. boulardii. Single factor experiment and Plackett-Burman design were conducted to obtain the optimal compound lyoprotectant formulations. The result showed that lactose, trehalose and sodium glutamate could significantly enhance the freeze-drying survival rate of S. boulardii. Meanwhile, all these three lyoprotectants showed positive effect on the freezedrying survival rate of the yeast, and the optimal lyoprotectant composition for S. boulardii was as follows: 18g/100mL lactose, 18g/100mL trehalose and 3g/100mL sodium glutamate.

  6. Human factors design guidelines for maintainability of Department of Energy nuclear facilities

    International Nuclear Information System (INIS)

    Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

    1985-01-01

    Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed

  7. Human factors design guidelines for maintainability of Department of Energy nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

    1985-06-18

    Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed.

  8. Greening Federal Facilities: An Energy, Environmental, and Economic Resource Guide for Federal Facility Managers and Designers; Second Edition

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, A.

    2001-05-16

    Greening Federal Facilities, Second Edition, is a nuts-and-bolts resource guide compiled to increase energy and resource efficiency, cut waste, and improve the performance of Federal buildings and facilities. The guide highlights practical actions that facility managers, design and construction staff, procurement officials, and facility planners can take to save energy and money, improve the comfort and productivity of employees, and benefit the environment. It supports a national effort to promote energy and environmental efficiency in the nation's 500,000 Federal buildings and facilities. Topics covered include current Federal regulations; environmental and energy decision-making; site and landscape issues; building design; energy systems; water and wastewater; materials; waste management, and recycling; indoor environmental quality; and managing buildings.

  9. Protease digestion from wheat stillage within a dry grind ethanol facility.

    Science.gov (United States)

    Bals, Bryan; Brehmer, Ben; Dale, Bruce; Sanders, Johan

    2011-01-01

    As the current starch based ethanol market increases at its rapid pace, finding new markets for the primary coproduct, distiller's grains, has gained considerable interest. One possibility is to isolate the protein-rich fraction for use as precursors to biochemicals and bioplastics, further decreasing fossil fuel consumption. This research focuses on enzymatic extraction of protein peptides from wheat heavy stillage using commercially available proteases. The energy saved due to this process ranged from ∼ 1.5 to 3.0 GJ/ton wheat stillage compared to fossil fuel-based chemicals. Using Protex 6L (Genencor), ∼ 57% of the protein in the stillage was soluble 24 h after protease addition at 0.1% w/w loading. Of these proteins, ∼ 32% were already soluble, indicating the importance of using wet heavy stillage as the feedstock rather than dried distiller's grains. Peptide size was less than 6 kDa. Further improvements in protein removal may be obtained through a fed batch addition of protease and improved protease cocktails. Copyright © 2011 American Institute of Chemical Engineers (AIChE).

  10. Preliminary Design of KAIST Micro Modular Reactor with Dry Air Cooling

    International Nuclear Information System (INIS)

    Baik, Seung Joon; Bae, Seong Jun; Kim, Seong Gu; Lee, Jeong Ik

    2014-01-01

    KAIST research team recently proposed a Micro Modular Reactor (MMR) concept which integrates power conversion unit (PCU) with the reactor core in a single module. Using supercritical CO 2 as a working fluid of cycle can achieve physically compact size due to small turbomachinery and heat exchangers. The objective of this project is to develop a concept that can operate at isolated area. The design focuses especially on the operation in the inland area where cooling water is insufficient. Thus, in this paper the potential for dry air cooling of the proposed reactor will be examined by sizing the cooling system with preliminary approach. The KAIST MMR is a recently proposed concept of futuristic SMR. The MMR size is being determined to be transportable with land transportation. Special attention is given to the MMR design on the dry cooling, which the cooling system does not depend on water. With appropriately designed air cooling heat exchanger, the MMR can operate autonomously. Two types of air cooling methods are suggested. One is using fan and the other is utilizing cooling tower for the air flow. With fan type air cooling method it consumes about 0.6% of generated electricity from the nuclear reactor. Cooling tower occupies an area of 227 m 2 and 59.6 m in height. This design is just a preliminary estimation of the dry cooling method, and therefore more detailed and optimal design will be followed in the next phase

  11. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  12. Application of the Quality by Design Approach to the Freezing Step of Freeze-Drying: Building the Design Space.

    Science.gov (United States)

    Arsiccio, Andrea; Pisano, Roberto

    2018-02-09

    The present work shows a rational method for the development of the freezing step of a freeze-drying cycle. The current approach to the selection of freezing conditions is still empirical and non-systematic, thus resulting in poor robustness of control strategy. The final aim of this work is to fill this gap, describing a rational procedure, based on mathematical modelling, for properly choosing the freezing conditions. Mechanistic models are used for the prediction of temperature profiles during freezing and dimension of ice crystals being formed. Mathematical description of the drying phase of freeze-drying is also coupled with results obtained by freezing models, thus providing a comprehensive characterization of the lyophilization process. In this framework, deep understanding of the phenomena involved is required, and, according to the Quality by Design approach, this knowledge can be used to build the design space. The step by step procedure for building the design space for freezing is thus described and examples of applications are provided. The calculated design space is validated upon experimental data and we show that it allows easy control of the freezing process and fast selection of appropriate operating conditions. Copyright © 2018. Published by Elsevier Inc.

  13. Ventilation design for Yucca Mountain Exploratory Studies Facility

    International Nuclear Information System (INIS)

    Jurani, R.S.

    1995-01-01

    Yucca Mountain, located in Southern Nevada approximately 160 km northwest of Las Vegas, is currently the site of intensive surface-based and underground investigations. The investigations are required to determine if the site is suitable for long term isolation of the Nation's high level nuclear waste inventory. A major component of the program is the Exploratory Studies Facility, or ESF. The ESF, when completed, will consist of approximately 25,600 meters of tunnels and drifts. The network of tunnels and drifts will house and support a wide array of testing programs conceived to provide physical information about the site. Information on geologic, geomechanical, and hydrologic data will be used in the repository design if the site is found suitable. Besides a few special requirements, the general ESF ventilation criteria during construction are similar to that of commercial tunneling and mining operations. The minimum air velocity at the Tunnel Boring Machine (TBM) and other active mining faces is 0.51 meter per second (m/s) (100 feet per minute [fpm]). Airways, estimated leakages and ventilation controls are converted into equivalent resistances for input to mine ventilation network computer simulations. VNETPC Version 3.1 computer software is used to generate the ventilation models for optimized system design and component selection. Subsequently, actual performance of the ventilation system will be verified and validated to comply with applicable nuclear regulatory quality assurance requirements. Dust control in the ESF is dependent on effective dust collection, enclosure, and airflow dilution. Minimum use of water, as feasible, is necessary to avoid adding moisture to the potential repository horizon. The limitation of water use for test drilling and TBM operation, and the rigid compliance with applicable federal and state regulations, make the ESF a ventilation design challenge

  14. Drying Western Red Cedar with Superheated Steam

    OpenAIRE

    Elustondo, Diego; Ahmed, Sheikh Ali; Oliveira, Luiz

    2014-01-01

    This exploratory study evaluated the possibility of drying 50-mm-thick western red cedar with superheated steam. Since there are no industrial facilities in Canada drying western red cedar with superheated steam, the study was designed to explore the potential of this technology in terms of lumber quality, moisture content distribution, and drying time. The experiments showed that the 50-mm-thick product can be dried in less than three days without jeopardizing lumber quality (in comparison w...

  15. Technical considerations in the design of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-11-01

    Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

  16. Potential for Ammonia Recapture by Farm Woodlands: Design and Application of a New Experimental Facility

    Directory of Open Access Journals (Sweden)

    Mark R. Theobald

    2001-01-01

    Full Text Available There has been increasing pressure on farmers in Europe to reduce the emissions of ammonia from their land. Due to the current financial climate in which farmers have to operate, it is important to identify ammonia control measures that can be adopted with minimum cost. The planting of trees around farmland and buildings has been identified as a potentially effective and low-cost measure to enhance ammonia recapture at a farm level and reduce long-range atmospheric transport. This work assesses experimentally what fraction of ammonia farm woodlands could potentially remove from the atmosphere. We constructed an experimental facility in southern Scotland to simulate a woodland shelterbelt planted in proximity to a small poultry unit. By measuring horizontal and vertical ammonia concentration profiles within the woodland, and comparing this to the concentration of an inert tracer (SF6 we estimate the depletion of ammonia due to dry deposition to the woodland canopy. Together with measurements of mean ammonia concentrations and throughfall fluxes of nitrogen, this information is used to provide a first estimate of the fraction of emitted ammonia that is recaptured by the woodland canopy. Analysis of these data give a lower limit of recapture of emitted ammonia, at the experimental facility, of 3%. By careful design of shelterbelt woodlands this figure could be significantly higher.

  17. Surface characteristics analysis of dry EDMed AISI D2 steel using modified tool design

    International Nuclear Information System (INIS)

    Pragadish, N.; Kumar, M. Pradeep

    2015-01-01

    A modified tool design is proposed which helps in drilling holes without any central core, and also enables the effective removal of the debris particles. Experiments were conducted on AISI D2 Steel using copper electrode as tool in both conventional EDM and dry EDM processes and the performance of both processes is compared. Experiments were designed using Taguchi's L27 orthogonal array. Discharge current (I), gap voltage (V), pulse on time (T ON ), gas pressure (P) and tool rotational speed (N) were chosen as the various input parameters, and their effect on the material removal rate (MRR), surface roughness (SR), surface morphology, microstructure and elemental composition of the machined surface is analyzed. The experimental results show better surface characteristics in the surface machined under dry EDM process.

  18. Radonclose - the system of Soviet designed regional waste management facilities

    International Nuclear Information System (INIS)

    Horak, W.C.; Reisman, A.; Purvis, E.E. III.

    1997-01-01

    The Soviet Union established a system of specialized regional facilities to dispose of radioactive waste generated by sources other than the nuclear fuel cycle. The system had 16 facilities in Russia, 5 in Ukraine, one in each of the other CIS states, and one in each of the Baltic Republics. These facilities are still being used. The major generators of radioactive waste they process these are research and industrial organizations, medical and agricultural institution and other activities not related to nuclear power. Waste handled by these facilities is mainly beta- and gamma-emitting nuclides with half lives of less than 30 years. The long-lived and alpha-emitting isotopic content is insignificant. Most of the radwaste has low and medium radioactivity levels. The facilities also handle spent radiation sources, which are highly radioactive and contain 95-98 percent of the activity of all the radwaste buried at these facilities

  19. Optimization and characterization of spray-dried IgG formulations: a design of experiment approach

    OpenAIRE

    Faghihi, Homa; Najafabadi, Abdolhosein Rouholamini; Vatanara, Alireza

    2017-01-01

    Background The purpose of the present study is to optimize a spray-dried formulation as a model antibody regarding stability and aerodynamic property for further aerosol therapy of this group of macromolecules. Method A three-factor, three-level, Box-Behnken design was employed milligrams of Cysteine (X1), Trehalose (X2), and Tween 20 (X3) as independent variables. The dependent variables were quantified and the optimized formulation was prepared accordingly. SEC-HPLC and FTIR-spectroscopy we...

  20. Solidification of hesperidin nanosuspension by spray drying optimized by design of experiment (DoE).

    Science.gov (United States)

    Wei, Qionghua; Keck, Cornelia M; Müller, Rainer H

    2018-01-01

    To accelerate the determination of optimal spray drying parameters, a "Design of Experiment" (DoE) software was applied to produce well redispersible hesperidin nanocrystals. For final solid dosage forms, aqueous liquid nanosuspensions need to be solidified, whereas spray drying is a large-scale cost-effective industrial process. A nanosuspension with 18% (w/w) of hesperidin stabilized by 1% (w/w) of poloxamer 188 was produced by wet bead milling. The sizes of original and redispersed spray-dried nanosuspensions were determined by laser diffractometry (LD) and photon correlation spectroscopy (PCS) and used as effect parameters. In addition, light microscopy was performed to judge the redispersion quality. After a two-step design of MODDE 9, screening model and response surface model (RSM), the inlet temperature of spray dryer and the concentration of protectant (polyvinylpyrrolidone, PVP K25) were identified as the most important factors affecting the redispersion of nanocrystals. As predicted in the RSM modeling, when 5% (w/w) of PVP K25 was added in an 18% (w/w) of hesperidin nanosuspension, subsequently spray-dried at an inlet temperature of 100 °C, well redispersed solid nanocrystals with an average particle size of 276 nm were obtained. By the use of PVP K25, the saturation solubility of the redispersed nanocrystals in water was improved to 86.81 µg/ml, about 2.5-fold of the original nanosuspension. In addition, the dissolution velocity was accelerated. This was attributed to the additional effects of steric stabilization on the nanocrystals and solubilization by the PVP polymer from spray drying.

  1. [Design of an HACCP program for a cocoa processing facility].

    Science.gov (United States)

    López D'Sola, Patrizia; Sandia, María Gabriela; Bou Rached, Lizet; Hernández Serrano, Pilar

    2012-12-01

    The HACCP plan is a food safety management tool used to control physical, chemical and biological hazards associated to food processing through all the processing chain. The aim of this work is to design a HACCP Plan for a Venezuelan cocoa processing facility.The production of safe food products requires that the HACCP system be built upon a solid foundation of prerequisite programs such as Good Manufacturing Practices (GMP) and Sanitation Standard Operating Procedures (SSOP). The existence and effectiveness of these prerequisite programs were previously assessed.Good Agriculture Practices (GAP) audit to cocoa nibs suppliers were performed. To develop the HACCP plan, the five preliminary tasks and the seven HACCP principles were accomplished according to Codex Alimentarius procedures. Three Critical Control Points (CCP) were identified using a decision tree: winnowing (control of ochratoxin A), roasting (Salmonella control) and metallic particles detection. For each CCP, Critical limits were established, the Monitoring procedures, Corrective actions, Procedures for Verification and Documentation concerning all procedures and records appropriate to these principles and their application was established. To implement and maintain a HACCP plan for this processing plant is suggested. Recently OchratoxinA (OTA) has been related to cocoa beans. Although the shell separation from the nib has been reported as an effective measure to control this chemical hazard, ochratoxin prevalence study in cocoa beans produced in the country is recommended, and validate the winnowing step as well

  2. Conceptual design report -- Gasification Product Improvement Facility (GPIF)

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, R.S.; Skinner, W.H.; House, L.S.; Duck, R.R. [CRS Sirrine Engineers, Inc., Greenville, SC (United States); Lisauskas, R.A.; Dixit, V.J. [Riley Stoker Corp., Worcester, MA (United States); Morgan, M.E.; Johnson, S.A. [PSI Technology Co., Andover, MA (United States). PowerServe Div.; Boni, A.A. [PSI-Environmental Instruments Corp., Andover, MA (United States)

    1994-09-01

    The problems heretofore with coal gasification and IGCC concepts have been their high cost and historical poor performance of fixed-bed gasifiers, particularly on caking coals. The Gasification Product Improvement Facility (GPIF) project is being developed to solve these problems through the development of a novel coal gasification invention which incorporates pyrolysis (carbonization) with gasification (fixed-bed). It employs a pyrolyzer (carbonizer) to avoid sticky coal agglomeration caused in the conventional process of gradually heating coal through the 400 F to 900 F range. In so doing, the coal is rapidly heated sufficiently such that the coal tar exists in gaseous form rather than as a liquid. Gaseous tars are then thermally cracked prior to the completion of the gasification process. During the subsequent endothermic gasification reactions, volatilized alkali can become chemically bound to aluminosilicates in (or added to) the ash. To reduce NH{sub 3} and HCN from fuel born nitrogen, steam injection is minimized, and residual nitrogen compounds are partially chemically reduced in the cracking stage in the upper gasifier region. Assuming testing confirms successful deployment of all these integrated processes, future IGCC applications will be much simplified, require significantly less mechanical components, and will likely achieve the $1,000/kWe commercialized system cost goal of the GPIF project. This report describes the process and its operation, design of the plant and equipment, site requirements, and the cost and schedule. 23 refs., 45 figs., 23 tabs.

  3. Advanced spray-dried design, physicochemical characterization, and aerosol dispersion performance of vancomycin and clarithromycin multifunctional controlled release particles for targeted respiratory delivery as dry powder inhalation aerosols.

    Science.gov (United States)

    Park, Chun-Woong; Li, Xiaojian; Vogt, Frederick G; Hayes, Don; Zwischenberger, Joseph B; Park, Eun-Seok; Mansour, Heidi M

    2013-10-15

    Respirable microparticles/nanoparticles of the antibiotics vancomycin (VCM) and clarithromycin (CLM) were successfully designed and developed by novel organic solution advanced spray drying from methanol solution. Formulation optimization was achieved through statistical experimental design of pump feeding rates of 25% (Low P), 50% (Medium P) and 75% (High P). Systematic and comprehensive physicochemical characterization and imaging were carried out using scanning electron microscopy (SEM), hot-stage microscopy (HSM), differential scanning calorimetry (DSC), X-ray powder diffraction (XRPD), Karl Fischer titration (KFT), laser size diffraction (LSD), gravimetric vapor sorption (GVS), confocal Raman microscopy (CRM) and spectroscopy for chemical imaging mapping. These novel spray-dried (SD) microparticulate/nanoparticulate dry powders displayed excellent aerosol dispersion performance as dry powder inhalers (DPIs) with high values in emitted dose (ED), respirable fraction (RF), and fine particle fraction (FPF). VCM DPIs displayed better aerosol dispersion performance compared to CLM DPIs which was related to differences in the physicochemical and particle properties of VCM and CLM. In addition, organic solution advanced co-spray drying particle engineering design was employed to successfully produce co-spray-dried (co-SD) multifunctional microparticulate/nanoparticulate aerosol powder formulations of VCM and CLM with the essential lung surfactant phospholipid, dipalmitoylphosphatidylcholine (DPPC), for controlled release pulmonary nanomedicine delivery as inhalable dry powder aerosols. Formulation optimization was achieved through statistical experimental design of molar ratios of co-SD VCM:DPPC and co-SD CLM:DPPC. XRPD and DSC confirmed that the phospholipid bilayer structure in the solid-state was preserved following spray drying. Co-SD VCM:DPPC and co-SD CLM:DPPC dry powder aerosols demonstrated controlled release of antibiotic drug that was fitted to various

  4. Design-only conceptual design report for pit disassembly and conversion facility. Rev 0

    Energy Technology Data Exchange (ETDEWEB)

    Zygmunt, S.; Christensen, L.; Richardson, C.

    1997-12-12

    This design-only conceptual design report (DOCDR) was prepared to support a funding request by the Department of Energy (DOE)-Office of Fissile Material Disposition (OFMD) for engineering design of the Pit Disassembly and Conversion Facility (PDCF) Project No. 99-D-141. The PDCF will be used to disassemble the nation`s inventory of surplus nuclear weapons pits and convert the plutonium recovered from those pits into a form suitable for storage, international inspection, and final disposition. The PDCF is a complex consisting of a hardened building that will contain the plutonium processes in a safe and secure manner, and conventional buildings and structures that will house support personnel, systems, and equipment. The PDCF uses the Advanced Recovery and Integrated Extraction System (ARIES), a low waste, modular pyroprocessing system to convert pits to plutonium oxide. The PDCF project consists of engineering and design, and construction of the buildings and structures, and engineering and design, procurement, installation, testing and start-up of equipment to disassemble pits and convert plutonium in pits to oxide form. The facility is planned to operate for 10 years, averaging 3.5 metric tons (3.86 tons) of plutonium metal per year. On conclusion of operations, the PDCF will be decontaminated and decommissioned.

  5. Proceedings of the US DOE/UK AEA Workshop on Facility Design

    Energy Technology Data Exchange (ETDEWEB)

    1986-11-01

    This document contains the proceeding of a Workshop on Facility Design that was held between the United States Department of Energy and the United Kingdom Atomic Energy Authority, Albuquerque, New Mexico, October 27--29, 1986. The intention of the workshop was to display relevant design criteria and to demonstrate for various US and UK facilities, current and projected criteria and how these criteria have been satisfied by facility design. Specific examples concern small plants, large plants, and waste stores.

  6. Assessing urban runoff program progress through a dry weather hybrid reconnaissance monitoring design.

    Science.gov (United States)

    Bernstein, Brock; Moore, Bruce; Sharp, Grant; Smith, Robert

    2009-10-01

    Characterizing dry weather conditions in urban Municipal Separate Storm Sewer Systems (MS4s), and then prioritizing and addressing problems due to urban pollutants, is a daunting challenge. The size and complexity of most MS4s and the ephemeral nature of many dry weather problems hamper efforts to identify and eliminate pollutant sources, and to track trends in condition. As a result, assessing overall program progress has proven difficult. We describe a hybrid dry weather urban monitoring design from southern California that combines probabilistic and targeted sampling to rigorously identify and prioritize problems and track program progress. Data from probabilistic sites define the urban background and establish tolerance intervals, which identify sites that persistently exceed the overall urban background. Targeted sites focus on locations where nearby activities and/or past history suggest that pollutant levels will be elevated. Embedding targeted monitoring within a probabilistic design enables data from targeted sites to be interpreted in a more meaningful regional context. Data from all sites are also used to construct site- and pollutant-specific control charts. These charts quickly identify instances where a site's behavior significantly changes, compared to its past behavior, suggesting an active source in the upstream drainage area. The hybrid design, and the use of formal statistical tools (tolerance intervals and control charts), permit the program to systematically prioritize problematic sites, compare conditions to the regional urban background, and track trends over time. In addition, the program's design allows several measures of program progress to be defined and thus consistently followed over time. Such hybrid designs can provide substantial advantages compared to more traditional monitoring approaches.

  7. Optimization and characterization of spray-dried IgG formulations: a design of experiment approach.

    Science.gov (United States)

    Faghihi, Homa; Najafabadi, Abdolhosein Rouholamini; Vatanara, Alireza

    2017-10-24

    The purpose of the present study is to optimize a spray-dried formulation as a model antibody regarding stability and aerodynamic property for further aerosol therapy of this group of macromolecules. A three-factor, three-level, Box-Behnken design was employed milligrams of Cysteine (X 1 ), Trehalose (X 2 ), and Tween 20 (X 3 ) as independent variables. The dependent variables were quantified and the optimized formulation was prepared accordingly. SEC-HPLC and FTIR-spectroscopy were conducted to evaluate the molecular and structural status of spray-dried preparations. Particle characterization of optimized sample was performed with the aid of DSC, SEM, and TSI examinations. Experimental responses of a total of 17 formulations resulted in yield values, (Y 1 ), ranging from 21.1 ± 0.2 to 40.2 ± 0.1 (%); beta-sheet content, (Y 2 ), from 66.22 ± 0.19 to 73.78 ± 0.26 (%); amount of aggregation following process, (Y 3 ), ranging from 0.11 ± 0.03 to 0.95 ± 0.03 (%); and amount of aggregation upon storage, (Y 4 ), from 0.81 ± 0.01 to 3.13 ± 0.64 (%) as dependent variables. Results-except for those of the beta sheet content-were fitted to quadratic models describing the inherent relationship between main factors. Co-application of Cysteine and Tween 20 preserved antibody molecules from molecular degradation and improved immediate and accelerated stability of spry-dried antibodies. Validation of the optimization study indicated high degree of prognostic ability of response surface methodology in preparation of stable spray-dried IgG. Graphical abstract Spray drying of IgG in the presence of Trehalose, Cysteine and Tween 20.

  8. Solid cellulose nanofiber based foams - Towards facile design of sustained drug delivery systems

    DEFF Research Database (Denmark)

    Svagan, Anna J; Benjamins, Jan-Willem; Al-Ansari, Zeinab

    2016-01-01

    -chemical properties that, when combined with surfactants, can be used to create very stable air bubbles and dry foams. Utilizing this inherent property, it is possible to modify the release kinetics of the model drug riboflavin in a facile way. Wet foams were prepared using cationic CNF and a pharmaceutically...

  9. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  10. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system

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

    CERN Document Server

    Miyamoto, Y; Harada, Y; Ikeno, K

    2002-01-01

    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.

  12. Development of risk-based decision methodology for facility design.

    Science.gov (United States)

    2014-06-01

    This report develops a methodology for CDOT to use in the risk analysis of various types of facilities and provides : illustrative examples for the use of the proposed framework. An overview of the current practices and applications to : illustrate t...

  13. Conceptual design report for the spent fuel management technology research and test (SMATER) facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, S.W.; Ro, S.G.; Lee, J.S.; Min, D.K.; Shin, Y.J. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-10-01

    This study was intended to develop concept for a pilot-scale remote operation facility for longer term management of spent fuel and therefrom to provide technical requirement for later basic design of the facility. Main scope of work for the study was to revise the past (1990) conceptual design in functions, scale, hot cell layout etc. based on user requirements. Technical reference was made to the PKA facility in Germany, through collaboration with appropriate partner, to elaborate the design and requirements. The study was focused on establishing design criteria and conceptual design of the SMATER facility. The results of this study should be an essential and useful basis upon optimization for further work to basic design of the facility. (author). 17 figs., 12 tabs.

  14. Design and fabrication of polymer based dry adhesives inspired by the gecko adhesive system

    Science.gov (United States)

    Jin, Kejia

    There has been significant interest in developing dry adhesives mimicking the gecko adhesive system, which offers several advantages compared to conventional pressure sensitive adhesives. Specifically, gecko adhesive pads have anisotropic adhesion properties: the adhesive pads (spatulae) stick strongly when sheared in one direction but are non-adherent when sheared in the opposite direction. This anisotropy property is attributed to the complex topography of the array of fine tilted and curved columnar structures (setae) that bear the spatulae. In this thesis, easy, scalable methods, relying on conventional and unconventional techniques are presented to incorporate tilt in the fabrication of synthetic polymer-based dry adhesives mimicking the gecko adhesive system, which provide anisotropic adhesion properties. In the first part of the study, the anisotropic adhesion and friction properties of samples with various tilt angles to test the validity of a nanoscale tape-peeling model of spatular function are measured. Consistent with the Peel Zone model, samples with lower tilt angles yielded larger adhesion forces. Contact mechanics of the synthetic array were highly anisotropic, consistent with the frictional adhesion model and gecko-like. Based on the original design, a new design of gecko-like dry adhesives was developed which showed superior tribological properties and furthermore showed anisotropic adhesive properties without the need for tilt in the structures. These adhesives can be used to reversibly suspend weights from vertical surfaces (e.g., walls) and, for the first time to our knowledge, horizontal surfaces (e.g., ceilings) by simultaneously and judiciously activating anisotropic friction and adhesion forces. Furthermore, adhesion properties between artificial gecko-inspired dry adhesives and rough substrates with varying roughness are studied. The results suggest that both adhesion and friction forces on a rough substrate depends significantly on the

  15. Conceptual design and neutronics analyses of a fusion reactor blanket simulation facility

    International Nuclear Information System (INIS)

    Beller, D.E.; Ott, K.O.; Terry, W.K.

    1987-01-01

    A new conceptual design of a fusion reactor blanket simulation facility has been developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBF), where experiments have resulted in the discovery of substantial deficiencies in neutronics predictions. With this design, discrepancies between calculation and experimental data can be nearly fully attributed to calculation methods because design deficiencies that could affect results are insignificant. The conceptual design of this FBBF analog, the Fusion Reactor Blanket Facility, is presented

  16. Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This DOE standard gives design and evaluation criteria for natural phenomena hazards (NPH) effects as guidance for implementing the NPH mitigation requirements of DOE 5480.28. Goal of the criteria is to assure that DOE facilities can withstand the effects of earthquakes, extreme winds, tornadoes, flooding, etc. They apply to the design of new facilities and the evaluation of existing facilities; they may also be used for modification and upgrading of the latter.

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

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  18. Engineering design of the Nova Laser Facility for inertial-confinement fusion

    International Nuclear Information System (INIS)

    Simmons, W.W.; Godwin, R.O.; Hurley, C.A.

    1982-01-01

    The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility

  19. Engineering design of the Nova Laser Facility for inertial-confinement fusion

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, W W; Godwin, R O; Hurley, C A; Wallerstein, E. P.; Whitham, K.; Murray, J. E.; Bliss, E. S.; Ozarski, R. G.; Summers, M. A.; Rienecker, F.; Gritton, D. G.; Holloway, F. W.; Suski, G. J.; Severyn, J. R.

    1982-01-25

    The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility.

  20. A performance goal-based seismic design philosophy for waste repository facilities

    International Nuclear Information System (INIS)

    Hossain, Q.A.

    1994-02-01

    A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and ''graded approach'' philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

  1. Value Engineering. "A Working Tool for Cost Control in the Design of Educational Facilities."

    Science.gov (United States)

    Lawrence, Jerry

    Value Engineering (VE) is a cost optimizing technique used to analyze design quality and cost-effectiveness. The application of VE procedures to the design and construction of school facilities has been adopted by the state of Washington. By using VE, the optimum value for every life cycle dollar spent on a facility is obtained by identifying not…

  2. Design of the Nonlinear Pin Rubber Forming Equipment Integrating the Functions of Extruding, Dewatering, Drying & Expanding

    Directory of Open Access Journals (Sweden)

    Yuefeng Yuan

    2014-12-01

    Full Text Available The top priority of car-tire suppliers is to improve wetland grip force of the using tires, reduce the rolling resistance and the rolling noise of tires. It is urgent for the tire industry to research and develop high-performance tires to solve the above problems. They must use the high- performance synthetic rubber and auxiliary rubber to develop the most advanced manufacturing technologies and equipment. Silica, a kind of important tire auxiliary rubber, can significantly reduce the rolling resistance of tires, improve the grip force and properties resistant to ice, wetness or slippery of tires. In this paper, based on the conventional tire rubber forming technologies of extrusion, dewatering, drying and expanding, a study is made on the conical screw, the dewatering barrel, the drying barrel, the pin layout scheme, the expanding die head, cutter and the control system. The nonlinear pin rubber forming equipment integrating the functions of extrusion, dewatering, drying and expanding is designed and applied to tire auxiliary rubber forming. The experiment shows that the forming device can realize the one-step forming, with high forming efficiency, low cost and less labor.

  3. Application of plackett-burman design in screening freeze drying cryoprotectants for Lactobacillus bulgaricus

    Directory of Open Access Journals (Sweden)

    Guowei SHU

    2015-08-01

    Full Text Available Lactobacillus bulgaricus is the bacteria commonly used in probiotic dairy product, including yogurt and cheese. The bacteria may be stored for long periods of time if it is freeze-dried. The cryoprotectant mixture for L. bulgaricus was optimized during the process of freeze-drying using a Plackett-Burman design and the steepest ascent test. In our initial tests, the cell survival rate and the number of viable cells were associated with the type of cyroprotectant used. Therefore, our optimization protocol focused on increasing survival rate. Substances that previously had a protective effect during freeze-drying were investigated, for example: sucrose, lactose, skim milk powder, sodium bicarbonate, sodium glutamate, magnesium sulfate, sodium ascorbate, yeast extract, vitamin B2, and phosphate buffer. We determined that the optimum cryoprotectant composition for L. bulgaricus consists of 28.0 g/100 mL skim milk powder, 24.0 g/100 mL lactose and 4.8 g/100 mL sodium ascorbate. The optimized cryoprotectant provides a 63.25% cell survival rate.

  4. Optimization of Chitosan Microspheres Spray Drying via 32 Full Factorial Design.

    Science.gov (United States)

    Katsarov, Plamen D; Pilicheva, Bissera A; Manev, Hristo M; Lukova, Paolina K; Kassarova, Margarita I

    2017-09-01

    Generally, the preparation of spray-dried microspheres is strongly affected by the process parameters. Particle size and production yield are mainly influenced by the spraying solution concentration and the pump rate of the spray dryer. The aim of this study was to assess optimum spray drying parameters - polymer concentration and pump rate required for the production of chitosan microspheres with high production yield and targeted for nasal administration particle size. Full 32 factorial design was used to study the investigated parameters. Three different concentrations of the chitosan solution were selected: a low concentration of 1%, average concentration of 1.5% and high concentration of 2%. The rate of the peristaltic pump was also varied at three levels: low rate of 10%, medium rate of 14% and high rate of 18%. Nine models of chitosan microspheres were formulated and characterized in terms of shape, surface morphology, size, particle size distribution and production yield. The particles obtained from 2% chitosan solutions, sprayed at 10% pump rate were of the highest yield (64.33%) and appropriate for nasal administration median diameter (3,434 μm). The two investigated spray-drying parameters interact with each other and their influence on the production yield and the size of the chitosan microspheres should be evaluated together, instead of one at a time. The assessed process parameters allow the production of chitosan microparticles with high yield and desirable characteristics (size, size distribution and shape) for intranasal delivery.

  5. 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

  6. Design Of Dry Cask Storage For Serpong Multipurpose Reactor Spent Nuclear Fuel

    Directory of Open Access Journals (Sweden)

    Dyah Sulistyani Rahayu

    2018-03-01

    Full Text Available DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear fuel (SNF from Serpong Multipurpose Reactor, after 100 days storing in the reactor pond, is transferred to water pool interim storage for spent fuel (ISFSF. At present there are a remaining of 245 elements of SNF on the ISSF,198 element of which have been re-exported to the USA. The dry-cask storage allows the SNF, which has already been cooled in the ISSF, to lower its radiation exposure and heat decayat a very low level. Design of the dry cask storage for SNF has been done. Dual purpose of unventilated vertical dry cask was selected among other choices of metal cask, horizontal concrete modules, and modular vaults by taking into account of technical and economical advantages. The designed structure of cask consists of SNF rack canister, inner steel liner, concrete shielding of cask, and outer steel liner. To avoid bimetallic corrosion, the construction material for canister and inner steel liner follows the same material construction of fuel cladding, i.e. the alloy of AlMg2. The construction material of outer steel liner is copper to facilitate the heat transfer from the cask to the atmosphere. The total decay heat is transferred from SNF elements bundle to the atmosphere by a serial of heat transfer resistance for canister wall, inner steel liner, concrete shielding, and outer steel liner respectedly. The rack canister optimum capacity of 34 fuel elements was designed by geometric similarity method basedon SNF position arrangement of 7 x 6 triangular pitch array of fuel elements for prohibiting criticality by spontaneous neutron. The SNF elements are stored vertically on the rack canister.  The thickness of concrete wall shielding was calculated by trial and error to give air temperature of 30 oC and radiation dose on the wall surface of outer liner of 200 mrem/h. The SNF elements bundles originate from the existing racks of wet storage, i

  7. 2001 - 2010 Design reference year for Denmark. [DRY]; 2001 - 2010 Design reference year for Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Riddersholm Wang, P.; Scharling, M.; Pagh Nielsen, K.

    2012-07-01

    This report presents the Danish Design Reference Year based on data from 2001 - 2010. It contains data set for technical dimensioning for the parameters global radiation, relative humidity, temperature and wind velocity, and diffuse solar radiation and illuminance. All data may be downloaded from www.dmi.dk/dmi/tr12-17.zip. (LN)

  8. 46 CFR 162.050-15 - Designation of facilities.

    Science.gov (United States)

    2010-10-01

    ... test equipment must not be a substantial factor in the facility's financial well being; (4) The... content of each sample using the method described in § 162.050-39 and report the value of each of the 12... paragraph (f)(2) of this section, the absolute value of Tn for each measurement, as determined by the...

  9. Conceptual design study of an integrated pyro-process facility at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    You, Gil-Sung; Choung, Won-Myung; Lee, Eun-Pyo; Cho, Il-Je; Kwon, Kie-Chan; Hong, Dong-Hee; Lee, Won-Kyung; Ku, Jeong-Hoe [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2009-06-15

    KAERI has been developing pyro-process facilities for a dry processing research of spent fuel about ten years since 1997. A hot cell facility, named the ACPF-Advanced spent fuel Conditioning Process Facility, for the demonstration of a head-end part of pyro-process was developed at November 2005. An inactive demonstration facility for the integrated pyro-process, named PRIDE-pyro-process Integrated inactive Demonstration, has been developing since 2007. The PRIDE facility consists of two cells: one is an air environment cell and another one is an argon environment cell. This facility includes several pyro-process equipment, such as a decladding/voloxidation device, a powder mixing device, an electro-reduction equipment, an electro-refining equipment, an electro-winning equipment, a Cd distillation equipment, a waste salt regeneration and solidification equipment, a salt distillation equipment, etc. In the cell and on the wall, some cell equipment, such as one cell crane, one BTDSM (Bridge Transported Dual arm Servo Manipulator), two HMSM (Horizontally Moving dual arm Servo Manipulator) will be also installed. This facility will be utilized to obtain the basic requirements for an engineering scale pyro-process facility in which the spent fuels from power reactors can be treated. (authors)

  10. Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

    Energy Technology Data Exchange (ETDEWEB)

    Smith, K.E.

    1994-03-21

    Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design.

  11. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  12. Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

    International Nuclear Information System (INIS)

    Smith, K.E.

    1994-01-01

    Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design

  13. Application of the MELCOR code to design basis PWR large dry containment analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  14. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1978-06-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially-severe impacts on plant operations are to be averted. This paper describes a facilities safeguards system suitable for production plant, in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely-coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides information and actions at the safeguards/operations interface

  15. Linear Accelerator Test Facility at LNF Conceptual Design Report

    CERN Document Server

    Valente, Paolo; Bolli, Bruno; Buonomo, Bruno; Cantarella, Sergio; Ceccarelli, Riccardo; Cecchinelli, Alberto; Cerafogli, Oreste; Clementi, Renato; Di Giulio, Claudio; Esposito, Adolfo; Frasciello, Oscar; Foggetta, Luca; Ghigo, Andrea; Incremona, Simona; Iungo, Franco; Mascio, Roberto; Martelli, Stefano; Piermarini, Graziano; Sabbatini, Lucia; Sardone, Franco; Sensolini, Giancarlo; Ricci, Ruggero; Rossi, Luis Antonio; Rotundo, Ugo; Stella, Angelo; Strabioli, Serena; Zarlenga, Raffaele

    2016-01-01

    Test beam and irradiation facilities are the key enabling infrastructures for research in high energy physics (HEP) and astro-particles. In the last 11 years the Beam-Test Facility (BTF) of the DA{\\Phi}NE accelerator complex in the Frascati laboratory has gained an important role in the European infrastructures devoted to the development and testing of particle detectors. At the same time the BTF operation has been largely shadowed, in terms of resources, by the running of the DA{\\Phi}NE electron-positron collider. The present proposal is aimed at improving the present performance of the facility from two different points of view: extending the range of application for the LINAC beam extracted to the BTF lines, in particular in the (in some sense opposite) directions of hosting fundamental physics and providing electron irradiation also for industrial users; extending the life of the LINAC beyond or independently from its use as injector of the DA{\\Phi}NE collider, as it is also a key element of the electron/...

  16. Structure and function design for nuclear facilities decommissioning information database

    International Nuclear Information System (INIS)

    Liu Yongkuo; Song Yi; Wu Xiaotian; Liu Zhen

    2014-01-01

    The decommissioning of nuclear facilities is a radioactive and high-risk project which has to consider the effect of radiation and nuclear waste disposal, so the information system of nuclear facilities decommissioning project must be established to ensure the safety of the project. In this study, by collecting the decommissioning activity data, the decommissioning database was established, and based on the database, the decommissioning information database (DID) was developed. The DID can perform some basic operations, such as input, delete, modification and query of the decommissioning information data, and in accordance with processing characteristics of various types of information data, it can also perform information management with different function models. On this basis, analysis of the different information data will be done. The system is helpful for enhancing the management capability of the decommissioning process and optimizing the arrangements of the project, it also can reduce radiation dose of the workers, so the system is quite necessary for safe decommissioning of nuclear facilities. (authors)

  17. Functional design criteria for an exploratory shaft facility in salt: Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    The purpose of the Functional Criteria for Design is to provide technical direction for the development of detailed design criteria for the exploratory shaft facility. This will assure that the exploratory shaft facility will be designed in accordance with the current Mission Plan as well as the Nuclear Waste Policy Act and 10 CFR Part 60, which will facilitate the licensing process. The functional criteria for design are not intended to limit or constrain the designer's flexibility. The following philosophies will be incorporated in the designs: (1) The exploratory shaft will be designed to fulfill its intended purpose which is to characterize the salt site by subsurface testing; (2) the design will minimize any adverse impact which the facility may cause to the environment and any damage to the site if it should be found suitable for a repository; (3) the health and safety of the public and of the workers will be an essential factor in the design; (4) sound engineering principles and practices will be consistently employed in the design process; (5) the exploratory shaft and related surface and subsurface facilities will be designed to be economical and reliable in construction, operation, and maintenance; and (6) the exploratory shaft facility will be designed in accordance with applicable federal, state, and local regulations, as well as all applicable national consensus codes and standards

  18. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  19. An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design

    International Nuclear Information System (INIS)

    Shipers, L.R.; Ottinger, C.A.; Sanchez, L.C.

    1993-01-01

    Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed

  20. Shielding calculations for the design of neutron radiography facility around PARR

    International Nuclear Information System (INIS)

    Ashraf, M.M.; Khan, A.R.

    1989-06-01

    Shielding calculations for neutron radiography facility, proposed to be established around PARR have been carried out using two group diffusion theory and shielding formulae. Gamma radiation penetration calculations have been carried out using simple attenuation methods. The fabrication and installation of the neutron radiography facility would provide the basis for designing a better collimating system and would help establish under water radiography facility for the inspection of highly radioactive materials and components etc. (orig./A.B.)

  1. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    Energy Technology Data Exchange (ETDEWEB)

    Bargalló, Enric, E-mail: enric.bargallo@esss.se [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, Jose Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Moya, Joaquin; Ibarra, Angel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain)

    2015-10-15

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  2. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    International Nuclear Information System (INIS)

    Bargalló, Enric; Arroyo, Jose Manuel; Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos; Moya, Joaquin; Ibarra, Angel

    2015-01-01

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  3. Integrating Lean Exploration Loops Into Healthcare Facility Design.

    Science.gov (United States)

    Mazur, Lukasz M; Johnson, Kendra; Pooya, Pegah; Chadwick, Janet; McCreery, John

    2017-04-01

    To explore what, when, and how Lean methods and tools can add value during the programming phase of design through providing additional resources and support to project leadership and the architectural design team. This case study-based research took place at one large academic hospital during design efforts of a surgical tower to house 19 operating rooms (ORs) and support spaces including pre- and postop, central processing and distribution, and materials management. Surgical services project leadership asked for support from Lean practitioners during the design process. Lean exploration loops (LELs) were conducted to generate evidence to support stakeholders, as they made important decisions about the new building design. The analyses conducted during LELs were primarily focused on the relative advantages of a large footprint with few floors or a smaller footprint with more floors and support spaces not collocated adjacent to ORs on the same floor. LELs resulted in quantifications of key operational and design features (e.g., design preferences of employees and patients, horizontal distance travel, and elevator utilization studies), which in turn complemented the architectural design process and created an opportunities to gain buy-in and consensus from stakeholders through their active participation in many of the analyses. We found Lean tools and methods to be of most value during programming phase when focused on the high-level operational and design issues to help establish buy-in and consensus among stakeholders, while acknowledging that there is often not enough design detail to perform accurate analysis.

  4. CNSC Design Requirements for Small Reactor Facilities (Focus on Differences from those for NPPs)

    International Nuclear Information System (INIS)

    Shim, Sang

    2013-01-01

    The Canadian Nuclear Safety Commission (CNSC) has established the regulatory framework for the efficient and effective licensing of all nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of all nuclear reactor facilities whether they are small reactor facilities or nuclear power plants (NPPs) regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities; and 2. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants. These regulatory documents have been modernized to document past practices and experience, and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper focuses on the key differences in the design requirements as applied to small reactor facilities in comparison with those applied to NPPs, in particular: 1) The application of a graded approach to make the documents applicable for a wide variety of designs, power levels and utilization associated with small reactor facilities; and 2) Utilization aspects associated with small reactor facilities. Finally, this paper presents some of the proposed considerations in design requirements to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were found unnecessary since the original version of these documents already contained requirements to address most of the lessons learned from the Fukushima event of March 2011

  5. Neutronics design and radiological aspects of HiPER facilities

    OpenAIRE

    Juarez Mañas, Rafael

    2013-01-01

    En este trabajo se han cubierto diferentes asuntos del diseño neutrónico de los aspectos radiológicos de las dos instalaciones del proyecto HiPER. El proyecto HiPER es un proyecto europeo concebido en el marco del programa ESFRI (European Scientific Facilities Research Infrastructure). Está destinado al desarrollo de la energía de fusión nuclear inercial mediante el uso de láseres y el esquema iluminación directa. Consecuentemente, se trata de una instalación con fines exclusivamente civiles....

  6. Assessment of requirement in the design of nuclear facilities

    International Nuclear Information System (INIS)

    Torikai, Kinichi

    1980-01-01

    Assessment of the requirements associated with decommissioning is made for cost and safety making comparison among those of construction, operation and decommissioning. Main principles of practice are easy access to facilities, easy separation of components, easy separation of contaminated parts from noncontaminated parts, and reduction in quantity of materials having contamination and induced activity. In practice now we are considering of a few points as follows: width of passage and angle of turning corner, free space around components, coated surface of concrete floor with impermeable paints, use of less induced materials for biological shield

  7. Designing for Optimal Energy Use in Production Facilities

    National Research Council Canada - National Science Library

    2004-01-01

    These briefing charts accompany a presentation on how Albert Kahn Associate saves its clients energy costs through building structure, design of HVAC systems, lighting systems, process related systems...

  8. Design of a solar-assisted drying system using the double-pass solar collector

    International Nuclear Information System (INIS)

    Sopian, K.; Daud, W.R.; Supranto; Othman, M.Y.; Yatim, B.

    2000-01-01

    A solar-assisted drying system that uses the double-pass solar collector with porous media in the second channel has been designed and constructed at the Solar Energy Research Park, Universiti Kebangsaan Malaysia. The drying system has a total of six double-pass solar collectors. Each collector has a length of 240 cm and a width of 120 cm. The upper channel depth is 3.5 cm and the lower channel depth is 10.5 cm. The lower channel is filled up with steel wool as the porous media. The solar collectors are arranged as 2 banks of 3 collectors each in series. Internal manifold are used to connect the collectors. An auxiliary heater source is installed to supply heat under unfavourable solar radiation conditions. An on/off controller is used to control the startup and shutdown of the auxiliary heater. An outlet temperature of 80-90 0 C can be achieved at a solar radiation range of 800-900 W/m 3 , ambient temperature of 29 degree C and flow rate of O.20 kg/s. (Author)

  9. Effect of Tube Diameter on The Design of Heat Exchanger in Solar Drying system

    Science.gov (United States)

    Husham Abdulmalek, Shaymaa; Khalaji Assadi, Morteza; Al-Kayiem, Hussain H.; Gitan, Ali Ahmed

    2018-03-01

    The drying of agriculture product consumes a huge fossil fuel rates that demand to find an alternative source of sustainable environmental friendly energy such as solar energy. This work presents the difference between using solar heat source and electrical heater in terms of design aspect. A circular-finned tube bank heat exchanger is considered against an electrical heater used as a heat generator to regenerate silica gel in solar assisted desiccant drying system. The impact of tube diameter on the heat transfer area was investigated for both the heat exchanger and the electrical heater. The fin performance was investigated by determining fin effectiveness and fin efficiency. A mathematical model was developed using MATLAB to describe the forced convection heat transfer between hot water supplied by evacuated solar collector with 70 °C and ambient air flow over heat exchanger finned tubes. The results revealed that the increasing of tube diameter augments the heat transfer area of both heat exchanger and electrical heater. The highest of fin efficiency was around 0.745 and the lowest was around 0.687 while the fin effectiveness was found to be around 0.998.

  10. Investigation of Film with β-Galactosidase Designed for Stabilization and Handling in Dry Configuration

    Directory of Open Access Journals (Sweden)

    Liguang Zhang

    2015-09-01

    Full Text Available Gelatin-based films with an immobilized enzyme designed for extending the stability of the protein in dry, non-powder configuration with precise dosing attributes were subjected to stress conditions of temperature and relative humidity. β-galactosidase was used as model functional protein. The film configuration preserved the activity of the enzyme under the different storage conditions investigated, which include room temperature under low (ambient and high (75% relative humidity, and 36 °C under low (oven and high relative humidity conditions for a period of 46 days. The influence of the enzyme and plasticizer (glycerol on the physical and mechanical properties of the films was investigated using DMA (dynamic mechanical analysis. Films containing 5% β-galactosisdase and glycerol concentrations of 14% or greater exhibited greater tensile strength, Young’s modulus, and elongation at break than films with equal concentrations of plasticizer but devoid of any enzyme. The surface texture of the films was analyzed using scanning electron microscopy (SEM. β-galactosidase and glycerol have opposite effects on the surface morphology of the films. Increasing concentrations of the enzyme result in rougher film surface, whereas increasing the concentration of glycerol leads to films with denser and smoother surface. The results obtained suggest that the dry film configuration approach can help in facilitating the stabilization, handling, storage, and transportation of functional proteins in a cost effective manner.

  11. On the Design of a Fuzzy Logic-Based Control System for Freeze-Drying Processes.

    Science.gov (United States)

    Fissore, Davide

    2016-12-01

    This article is focused on the design of a fuzzy logic-based control system to optimize a drug freeze-drying process. The goal of the system is to keep product temperature as close as possible to the threshold value of the formulation being processed, without trespassing it, in such a way that product quality is not jeopardized and the sublimation flux is maximized. The method involves the measurement of product temperature and a set of rules that have been obtained through process simulation with the goal to obtain a unique set of rules for products with very different characteristics. Input variables are the difference between the temperature of the product and the threshold value, the difference between the temperature of the heating fluid and that of the product, and the rate of change of product temperature. The output variables are the variation of the temperature of the heating fluid and the pressure in the drying chamber. The effect of the starting value of the input variables and of the control interval has been investigated, thus resulting in the optimal configuration of the control system. Experimental investigation carried out in a pilot-scale freeze-dryer has been carried out to validate the proposed system. Copyright © 2016 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

  12. Safety and environmental process for the design and construction of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Brereton, S.J., LLNL

    1998-05-27

    The National Ignition Facility (NIF) is a U.S. Department of Energy (DOE) laser fusion experimental facility currently under construction at the Lawrence Livermore National Laboratory (LLNL). This paper describes the safety and environmental processes followed by NIF during the design and construction activities.

  13. Design and Development of a New Facility for Teaching and Research in Clinical Anatomy

    Science.gov (United States)

    Greene, John Richard T.

    2009-01-01

    This article discusses factors in the design, commissioning, project management, and intellectual property protection of developments within a new clinical anatomy facility in the United Kingdom. The project was aimed at creating cost-effective facilities that would address widespread concerns over anatomy teaching, and support other activities…

  14. Encapsulation plant preliminary design, phase 2. Repository connected facility

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-12-01

    The disposal facility of the spent nuclear fuel will be located in Olkiluoto. The encapsulation plant is a part of the disposal facility. In this report, an independent encapsulation plant is located above the underground repository. In the encapsulation plant, the spent fuel is received and treated for disposal. In the fuel handling cell, the spent fuel assemblies are unloaded from the spent fuel transport casks and loaded into the disposal canisters. The gas atmosphere of the disposal canister is changed, the bolted inner canister lid is closed, and the electron beam welding method is used to close the lid of the outer copper canister. The disposal canisters are cleaned and transferred into the buffer store after the machining and inspection of the copper lid welds. From the buffer store, the disposal canisters are transferred into the repository spaces by help of the canister lift. All needed stages of operation are to be performed safely without any activity releases or remarkable personnel doses. The bentonite block interim storage is associated with the encapsulation plant. The bentonite blocks are made from bentonite powder. The bentonite blocks are used as buffer material around the disposal canister in the deposition hole. The average production rate of the encapsulation plant is 40 canisters per year. The nominal maximum production capacity is 100 canisters per year in one shift operation. (orig.)

  15. Design and construction of an urban runoff research facility.

    Science.gov (United States)

    Wherley, Benjamin G; White, Richard H; McInnes, Kevin J; Fontanier, Charles H; Thomas, James C; Aitkenhead-Peterson, Jacqueline A; Kelly, Steven T

    2014-08-08

    As the urban population increases, so does the area of irrigated urban landscape. Summer water use in urban areas can be 2-3x winter base line water use due to increased demand for landscape irrigation. Improper irrigation practices and large rainfall events can result in runoff from urban landscapes which has potential to carry nutrients and sediments into local streams and lakes where they may contribute to eutrophication. A 1,000 m(2) facility was constructed which consists of 24 individual 33.6 m(2) field plots, each equipped for measuring total runoff volumes with time and collection of runoff subsamples at selected intervals for quantification of chemical constituents in the runoff water from simulated urban landscapes. Runoff volumes from the first and second trials had coefficient of variability (CV) values of 38.2 and 28.7%, respectively. CV values for runoff pH, EC, and Na concentration for both trials were all under 10%. Concentrations of DOC, TDN, DON, PO₄₋P, K(+), Mg(2+), and Ca(2+) had CV values less than 50% in both trials. Overall, the results of testing performed after sod installation at the facility indicated good uniformity between plots for runoff volumes and chemical constituents. The large plot size is sufficient to include much of the natural variability and therefore provides better simulation of urban landscape ecosystems.

  16. A Design of Experiment approach to predict product and process parameters for a spray dried influenza vaccine.

    Science.gov (United States)

    Kanojia, Gaurav; Willems, Geert-Jan; Frijlink, Henderik W; Kersten, Gideon F A; Soema, Peter C; Amorij, Jean-Pierre

    2016-09-25

    Spray dried vaccine formulations might be an alternative to traditional lyophilized vaccines. Compared to lyophilization, spray drying is a fast and cheap process extensively used for drying biologicals. The current study provides an approach that utilizes Design of Experiments for spray drying process to stabilize whole inactivated influenza virus (WIV) vaccine. The approach included systematically screening and optimizing the spray drying process variables, determining the desired process parameters and predicting product quality parameters. The process parameters inlet air temperature, nozzle gas flow rate and feed flow rate and their effect on WIV vaccine powder characteristics such as particle size, residual moisture content (RMC) and powder yield were investigated. Vaccine powders with a broad range of physical characteristics (RMC 1.2-4.9%, particle size 2.4-8.5μm and powder yield 42-82%) were obtained. WIV showed no significant loss in antigenicity as revealed by hemagglutination test. Furthermore, descriptive models generated by DoE software could be used to determine and select (set) spray drying process parameter. This was used to generate a dried WIV powder with predefined (predicted) characteristics. Moreover, the spray dried vaccine powders retained their antigenic stability even after storage for 3 months at 60°C. The approach used here enabled the generation of a thermostable, antigenic WIV vaccine powder with desired physical characteristics that could be potentially used for pulmonary administration. Copyright © 2016 The Authors. Published by Elsevier B.V. All rights reserved.

  17. Preliminary design for hot dirty-gas control-valve test facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

  18. Implementation of decommissioning criteria in the conceptual design of the MRS facility

    International Nuclear Information System (INIS)

    Gross, D.L.; Wilcox, A.D.; Huang, S.

    1986-01-01

    The US Department of Energy (DOE) selected the Ralph M. Parsons Company (RMP) to prepare the conceptual design of the Monitored Retrievable Storage (MRS) Facility. The purpose of this facility is to consolidate and temporarily store spent fuel from civilian nuclear power plants. In addition, it will overpack, handle, and store high-level radioactive waste from non-defense related sources. The Functional Design Criteria (FDC) prepared by Pacific Northwest Laboratories, as well as 10 CFR 72, requires the facility to be designed for decommissioning, with provisions to facilitate decontamination of structures and equipment to minimize the volume of radioactive wastes and contaminated equipment at the time of decommissioning. Many problems associated with decommissioning a nuclear facility have been identified in recent years and the design for the MRS Facility presents a unique opportunity for RMP to implement decommissioning criteria into the conceptual design of a major nuclear facility. The provisions made in the design to facilitate decommissioning include good housekeeping during operations, controlled personnel access, access for equipment removal, equipment design, installed radiation monitors, adequate work space, installed decontamination systems and areas, control of all effluents, and operational documentation. These topics will be the major points of discussion for this paper

  19. Fabrication and performance analysis of a DEA cuff designed for dry-suit applications

    International Nuclear Information System (INIS)

    Ahmadi, S; Camacho Mattos, A; Barbazza, A; Soleimani, M; Boscariol, P; Menon, C

    2013-01-01

    A method for manufacturing a cylindrical dielectric elastomer actuator (DEA) is presented. The cylindrical DEA can be used in fabricating the cuff area of dry-suits where the garment is very tight and wearing the suit is difficult. When electrically actuated, the DEA expands radially and the suit can be worn more comfortably. In order to study the performance of the DEA, a customized testing setup was designed, and silicone-made cuff samples with different material stiffnesses were tested. Analytical and FEM modeling were considered to evaluate the experimental output. The results revealed that although the stiffness of the DEA material has a direct relationship with the radial constrictive pressure caused by mechanically stretching the DEA, it has a minor effect on the actuation pressure. It was also found that stacking multiple layers of the DEA to fabricate a laminated structure enabled the attainment of a desired variation of pressure required for the implementation of an electrically tunable cuff. (paper)

  20. 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)

  1. LMFBR safety testing needs and the conceptual design of a new safety research experiment facility

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Matlock, R.G.; Goldman, A.J.

    1975-09-01

    Experiment needs for the LMFBR safety program are reviewed. The screening of reactor concepts which would meet the needs is described and a conceptual design for a new safety research experiment facility is presented

  2. Consistent natural phenomena design and evaluation guidelines for U.S. Department of Energy facilities

    International Nuclear Information System (INIS)

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

    1989-01-01

    Uniform design and evaluation guidelines for protection against natural phenomena hazards such as earthquakes, extreme winds, and flooding for facilities at Department of Energy (DOE) sites throughout the United States have been developed. The guidelines apply to design of new facilities and to evaluation or modification of existing facilities. These guidelines are an approach for design or evaluation for mitigating the effects of natural phenomena hazards. These guidelines are intended to control the level of conservatism introduced in the design/evaluation process such that all hazards are treated on a reasonably consistent and uniform basis and such that the level of conservatism is appropriate for facility characteristics such as importance, cost, and hazards to on-site personnel, the general public, and the environment. The philosophy and goals of these guidelines are covered by this paper

  3. Oak Ridge low-level waste disposal facility designs

    International Nuclear Information System (INIS)

    Van Hoesen, S.D.; Jones, L.S.

    1991-01-01

    The strategic planning process that culuminates in the identification, selection, construction, and ultimate operation of treatment, storage, and disposal facilities for all types of low-level waste (LLW) generated on the Oak Ridge Reservation (ORR) was conducted under the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. This program considered management of various concentrations of short half-life radionuclides generated principally at Oak Ridge National Laboratory (ORNL) and long half-life radionuclides (principally uranium) generated at the Oak Ridge Y-12 Plant and the Oak Ridge K-25 Plant. The LLWDDD Program is still ongoing and involves four phases: (1) alternative identification and evaluation, (2) technology demonstration, (3) limited operational implementation, and (4) full operational implementation. This document provides a discussion of these phases

  4. Fort Hood solar cogeneration facility conceptual design study

    Energy Technology Data Exchange (ETDEWEB)

    1981-05-01

    A study is done on the application of a tower-focus solar cogeneration facility at the US Fort Hood Army Base in Killeen, Texas. Solar-heated molten salt is to provide the steam for electricity and for room heating, room cooling, and domestic hot water. The proposed solar cogeneration system is expected to save the equivalent of approximately 10,500 barrels of fuel oil per year and to involve low development risks. The site and existing plant are described, including the climate and plant performance. The selection of the site-specific configuration is discussed, including: candidate system configurations; technology assessments, including risk assessments of system development, receiver fluids, and receiver configurations; system sizing; and the results of trade studies leading to the selection of the preferred system configuration. (LEW)

  5. Design of dry scroll vacuum pumping system for efficient pumping of corrosive gas at medium vacuum range

    International Nuclear Information System (INIS)

    Banerjee, I.; Chandresh, B.G.; Guha, K.C.; Sarkar, S.

    2015-01-01

    Dry vacuum pumping systems attracts many applications because of its inherent capability of corrosion free pumping. It becomes a common trait of application in Thermo Nuclear Fusion, Semi conductor, Isotope separation industries etc. Thermo nuclear fusion requires a train of specially sealed roots pump backed by suitable capacity dry screw or reciprocating pump. Similarly corrosive fluoride gas pumping requires hermetically sealed specially designed dry scroll vacuum pump. Plant emergency operation however involves train of specially sealed roots pump backed with scroll pump for faster evacuation. In our attempt an indigenously designed scroll pump and associated system are designed to pump corrosive gases in a way to confine the corrosion product within the system. In order to execute the design, a numerical code for low pressure application is developed

  6. Acoustics in Research Facilities--Control of Wanted and Unwanted Sound. Laboratory Design Notes.

    Science.gov (United States)

    Newman, Robert B.

    Common and special acoustics problems are discussed in relation to the design and construction of research facilities. Following a brief examination of design criteria for the control of wanted and unwanted sound, the technology for achieving desired results is discussed. Emphasis is given to various design procedures and materials for the control…

  7. Exploring Operational Safeguards, Safety, and Security by Design to Address Real Time Threats in Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Schanfein, Mark J.; Mladineo, Stephen V.

    2015-07-07

    Over the last few years, significant attention has been paid to both encourage application and provide domestic and international guidance for designing in safeguards and security in new facilities.1,2,3 However, once a facility is operational, safeguards, security, and safety often operate as separate entities that support facility operations. This separation is potentially a serious weakness should insider or outsider threats become a reality.Situations may arise where safeguards detects a possible loss of material in a facility. Will they notify security so they can, for example, check perimeter doors for tampering? Not doing so might give the advantage to an insider who has already, or is about to, move nuclear material outside the facility building. If outsiders break into a facility, the availability of any information to coordinate the facility’s response through segregated alarm stations or a failure to include all available radiation sensors, such as safety’s criticality monitors can give the advantage to the adversary who might know to disable camera systems, but would most likely be unaware of other highly relevant sensors in a nuclear facility.This paper will briefly explore operational safeguards, safety, and security by design (3S) at a high level for domestic and State facilities, identify possible weaknesses, and propose future administrative and technical methods, to strengthen the facility system’s response to threats.

  8. A reliable facility location design model with site-dependent disruption in the imperfect information context

    Science.gov (United States)

    Yun, Lifen; Wang, Xifu; Fan, Hongqiang; Li, Xiaopeng

    2017-01-01

    This paper proposes a reliable facility location design model under imperfect information with site-dependent disruptions; i.e., each facility is subject to a unique disruption probability that varies across the space. In the imperfect information contexts, customers adopt a realistic “trial-and-error” strategy to visit facilities; i.e., they visit a number of pre-assigned facilities sequentially until they arrive at the first operational facility or give up looking for the service. This proposed model aims to balance initial facility investment and expected long-term operational cost by finding the optimal facility locations. A nonlinear integer programming model is proposed to describe this problem. We apply a linearization technique to reduce the difficulty of solving the proposed model. A number of problem instances are studied to illustrate the performance of the proposed model. The results indicate that our proposed model can reveal a number of interesting insights into the facility location design with site-dependent disruptions, including the benefit of backup facilities and system robustness against variation of the loss-of-service penalty. PMID:28486564

  9. A performance goal-based seismic design philosophy for waste repository facilities

    International Nuclear Information System (INIS)

    Hossain, Q.A.

    1994-01-01

    A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and open-quotes graded approachclose quotes philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

  10. Incorporating functional requirements into the structural design of the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Hsiu, F.J.; Ng, C.K.; Almuti, A.M.

    1986-01-01

    Vitrification Building-type structures have unique features and design needs. The structural design requires new concepts and custom detailing. The above special structural designs have demonstrated the importance of the five design considerations listed in the introduction. Innovative ideas and close coordination are required to achieve the design objectives. Many of these innovations have been applied to the DWPF facility which is a first of a kind

  11. Is designation of origin an important cue driving consumer loyalty behaviour? Evidence from scanner data on dry-cured ham

    DEFF Research Database (Denmark)

    Chrysochou, Polymeros; Giraud, Georges

    2007-01-01

    designation of origin influences their actual purchase behaviour and, moreover, behavioural loyalty towards them. For measuring loyalty we applied the Dirichlet model on scanner supermarket data on dry-cured ham, a common local French food product. Results show that designation of origin...... is not that an important driver of loyalty comparing to price and brand name....

  12. Design of Temperature Measurement System on the Drying Process of Madura Tobacco Leaves

    OpenAIRE

    Wardana, Humadillah Kurniadi; Endarko, Endarko

    2015-01-01

    The quality of dried chopped leaves of tobacco is an important factor. The present work developed an oven for drying process to measure and evalute on drying shrinkage characteristic of choped leaves Madura tobacco. The oven has three racks for analyzing and monitoring the rate of drying shrinkage of Madura tobacco. Every rack has a different amount of chopped leaves as follows: 120 g on top rack, 100 g for middle rack and 80 g for bottom rack. Rate of drying shrinkage was analyzed for 20 min...

  13. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    The Regulatory Assessment Document (RAD) was developed to provide assurance that the design meets the requirements of 10 CFR 72 as amended or clarified in the Federal Register (FR) and will not cause an undue risk to the health and safety of the public and workers during normal or off-normal operations. The RAD also fulfills the requirements of DOE Orders 6430 and 5481.1A, which require a preliminary safety evaluation of new projects be conducted to identify hazards or potential accidents and to describe and analyze the adequacy of the design to eliminate, control, or mitigate those hazards or accidents and/or their consequences. The results of this preliminary assessment thus provide a precursor to final design development, including special safety features to ensure the safety of operating personnel and the general public. 1 tab

  14. Radiological implications of contact maintenance: Impacts on facility design

    International Nuclear Information System (INIS)

    Brown, R.C.

    1994-01-01

    The purpose of this document is to provide an initial, rough order of magnitude, evaluation of the relationship between the concentrations of selected radionuclides in process streams of a chemical process plant and the required degree of protective features for plant operations personnel. The evaluation provided in this document specifies ''trigger level'' concentrations of 90 Sr, 137 Cs, and transuranics (TRU) for ''contact maintenance'' activities. Concentrations above the ''trigger levels'' can be accommodated provided offsetting design features are incorporated (e.g., improved shielding partial to total confinement, etc.). This information will assist in defining the degree of reduction of concentrations of radionuclides required for the feed used in a low-level liquid waste processing plant to utilize a contact maintenance design concept. Offsetting design features that influence maintenance personnel exposures in a contact maintenance situation are identified. All concentrations are expressed in terms of actual process fluids before any flushing and decontamination steps

  15. Monte Carlo simulations for design of the KFUPM PGNAA facility

    CERN Document Server

    Naqvi, A A; Maslehuddin, M; Kidwai, S

    2003-01-01

    Monte Carlo simulations were carried out to design a 2.8 MeV neutron-based prompt gamma ray neutron activation analysis (PGNAA) setup for elemental analysis of cement samples. The elemental analysis was carried out using prompt gamma rays produced through capture of thermal neutrons in sample nuclei. The basic design of the PGNAA setup consists of a cylindrical cement sample enclosed in a cylindrical high-density polyethylene moderator placed between a neutron source and a gamma ray detector. In these simulations the predominant geometrical parameters of the PGNAA setup were optimized, including moderator size, sample size and shielding of the detector. Using the results of the simulations, an experimental PGNAA setup was then fabricated at the 350 kV Accelerator Laboratory of this University. The design calculations were checked experimentally through thermal neutron flux measurements inside the PGNAA moderator. A test prompt gamma ray spectrum of the PGNAA setup was also acquired from a Portland cement samp...

  16. The design of diagnostic imaging and nuclear medicine facilities in a major new teaching hospital

    International Nuclear Information System (INIS)

    Causer, D.A.

    2010-01-01

    Full text: The design of the layout and radiation shielding for diagnostic imaging and nuclear medicine facilities in a modern teaching hospital requires the collaboration of persons from a number of professions including architects, engineers, radiologists, nuclear medicine physi cians, medical imaging technologists and medical physicists. This paper discusses the design of such facilities, including PET/CT and T-131 ablation therapy suites for a major new tertiary hospital in Perth. The importance of involving physicists on the planning team from the earliest stages of the design process is stressed, design plans presented, and some of the problems which may present themselves and their solutions are illustrated.

  17. Building Design Guidelines for Interior Architecture Concerned with Animal Researches Facilities

    International Nuclear Information System (INIS)

    ElDib, A.A. E.

    2014-01-01

    This paper discusses the most important design guidelines elements and characteristics for animal facilities, in order to achieve and maintain highest efficiency can be, with respect to the pivot role of Interior Architecture as one of the accurate specializations for completing the Architectural Sciences, for designer/s concerned with those types of facilities, (specially those using radioactive materials). These building types known as vivariums, are specially designed, accommodating and having sophisticated controlled environments for the care and maintenance of experimental animals, and are related to, but distinct from other research laboratories premises

  18. Conceptual Design of an Antiproton Generation and Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Peggs, Stephen

    2006-10-24

    The Antiproton Generation and Storage Facility (AGSF) creates copious quantities of antiprotons, for bottling and transportation to remote cancer therapy centers. The first step in the generation and storage process is to accelerate an intense proton beam down the Main Linac for injection into the Main Ring, which is a Rapid Cycling Synchrotron that accelerates the protons to high energy. The beam is then extracted from the ring into a transfer line and into a Proton Target. Immediately downstream of the target is an Antiproton Collector that captures some of the antiprotons and focuses them into a beam that is transported sequentially into two antiproton rings. The Precooler ring rapidly manipulates antiproton bunches from short and broad (in momentum) to long and thin. It then performs some preliminary beam cooling, in the fraction of a second before the next proton bunch is extracted from the Main Ring. Pre-cooled antiprotons are passed on to the Accumulator ring before the next antiprotons arrive from the target. The Accumulator ring cools the antiprotons, compressing them into a dense state that is convenient for mass storage over many hours. Occasionally the Accumulator ring decelerates a large number of antiprotons, injecting them into a Deceleration Linac that passes them into a waiting Penning trap.

  19. Conceptual Design of an Antiproton Generation and Storage Facility

    International Nuclear Information System (INIS)

    Peggs, Stephen

    2006-01-01

    The Antiproton Generation and Storage Facility (AGSF) creates copious quantities of antiprotons, for bottling and transportation to remote cancer therapy centers. The first step in the generation and storage process is to accelerate an intense proton beam down the Main Linac for injection into the Main Ring, which is a Rapid Cycling Synchrotron that accelerates the protons to high energy. The beam is then extracted from the ring into a transfer line and into a Proton Target. Immediately downstream of the target is an Antiproton Collector that captures some of the antiprotons and focuses them into a beam that is transported sequentially into two antiproton rings. The Precooler ring rapidly manipulates antiproton bunches from short and broad (in momentum) to long and thin. It then performs some preliminary beam cooling, in the fraction of a second before the next proton bunch is extracted from the Main Ring. Pre-cooled antiprotons are passed on to the Accumulator ring before the next antiprotons arrive from the target. The Accumulator ring cools the antiprotons, compressing them into a dense state that is convenient for mass storage over many hours. Occasionally the Accumulator ring decelerates a large number of antiprotons, injecting them into a Deceleration Linac that passes them into a waiting Penning trap

  20. Conceptual design report for the away from reactor spent fuel storage facility, Savannah River Plant

    International Nuclear Information System (INIS)

    1978-12-01

    The Department of Energy (DOE) requested that Du Pont prepare a conceptual design and appraisal of cost for Federal budget planning for an away from reactor spent fuel storage facility that could be ready to store fuel by December 1982. This report describes the basis of the appraisal of cost in the amount of $270,000,000 for all facilities. The proposed action is to provide a facility at the Savannah River Plant. The facility will have an initial storage capacity of 5000 metric tons of spent fuel and will be capable of receiving 1000 metric tons per year. The spent fuel will be stored in water-filled concrete basins that are lined with stainless steel. The modular construction of the facility will allow future expansion of the storage basins and auxiliary services in a cost-effective manner. The facility will be designed to receive, handle, decontaminate and reship spent fuel casks; to remove irradiated fuel from casks; to place the fuel in a storage basin; and to cool and control the quality of the water. The facility will also be designed to remove spent fuel from storage basins, load the spent fuel into shipping casks, decontaminated loaded casks and ship spent fuel. The facility requires a license by the Nuclear Regulatory Commission (NRC). Features of the design, construction and operations that may affect the health and safety of the workforce and the public will conform with NRC requirements. The facility would be ready to store fuel by January 1983, based on normal Du Pont design and construction practices for DOE. The schedule does not include the effect of licensing by the NRC. To maintain this option, preparation of the documents and investigation of a site at the Savannah River Plant, as required for licensing, were started in FY '78

  1. Process Design Manual: Wastewater Treatment Facilities for Sewered Small Communities.

    Science.gov (United States)

    Leffel, R. E.; And Others

    This manual attempts to describe new treatment methods, and discuss the application of new techniques for more effectively removing a broad spectrum of contaminants from wastewater. Topics covered include: fundamental design considerations, flow equalization, headworks components, clarification of raw wastewater, activated sludge, package plants,…

  2. The ITER neutral beam test facility: Designs of the general infrastructure, cryosystem and cooling plant

    International Nuclear Information System (INIS)

    Cordier, J.J.; Hemsworth, R.; Chantant, M.; Gravil, B.; Henry, D.; Sabathier, F.; Doceul, L.; Thomas, E.; Houtte, D. van; Zaccaria, P.; Antoni, V.; Bello, S. Dal; Marcuzzi, D.; Antipenkov, A.; Day, C.; Dremel, M.; Mondino, P.L.

    2005-01-01

    The CEA Association is involved, in close collaboration with ENEA, FZK, IPP and UKAEA European Associations, in the first ITER neutral beam (NB) injector and the ITER neutral beam test facility design (EFDA task ref. TW3-THHN-IITF1). A total power of about 50 MW will have to be removed in steady state on the neutral beam test facility (NBTF). The main purpose of this task is to make progress with the detailed design of the first ITER NB injector and to start the conceptual design of the ITER NBTF. The general infrastructure layout of a generic site for the NBTF includes the test facility itself equipped with a dedicated beamline vessel [P.L. Zaccaria, et al., Maintenance schemes for the ITER neutral beam test facility, this conference] and integration studies of associated auxiliaries such as cooling plant, cryoplant and forepumping system

  3. Conceptual Design of an In-Space Cryogenic Fluid Management Facility

    Science.gov (United States)

    Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

    1981-01-01

    The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is presented. The proposed facility consisting of a supply tank, receiver tank, pressurization system, instrumentation, and supporting hardware, is described. The experimental objectives, the receiver tank to be modeled, and constraints imposed on the design by the space shuttle, Spacelab, and scaling requirements, are described. The conceptual design, including the general configurations, flow schematics, insulation systems, instrumentation requirements, and internal tank configurations for the supply tank and the receiver tank, is described. Thermal, structural, fluid, and safety and reliability aspects of the facility are analyzed. The facility development plan, including schedule and cost estimates for the facility, is presented. A program work breakdown structure and master program schedule for a seven year program are included.

  4. Design and evaluation guidelines for Department of Energy facilities subjected to natural phenomena hazards

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Murray, R.C.; Hill, J.R.

    1990-06-01

    The Department of Energy (DOE) and the DOE Natural Phenomena Hazards Panel have developed uniform design and evaluation guidelines for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of the guidelines is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. The guidelines apply to both new facilities (design) and existing facilities (evaluation, modification, and upgrading). The intended audience is primarily the civil/structural or mechanical engineers conducting the design or evaluation of DOE facilities. The likelihood of occurrence of natural phenomena hazards at each DOE site has been evaluated by the DOE Natural Phenomena Hazard Program. Probabilistic hazard models are available for earthquake, extreme wind/tornado, and flood. Alternatively, site organizations are encouraged to develop site-specific hazard models utilizing the most recent information and techniques available. In this document, performance goals and natural hazard levels are expressed in probabilistic terms, and design and evaluation procedures are presented in deterministic terms. Design/evaluation procedures conform closely to common standard practices so that the procedures will be easily understood by most engineers. Performance goals are expressed in terms of structure or equipment damage to the extent that: (1) the facility cannot function; (2) the facility would need to be replaced; or (3) personnel are endangered. 82 refs., 12 figs., 18 tabs

  5. Design and evaluation guidelines for Department of Energy facilities subjected to natural phenomena hazards

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, R.P. (Structural Mechanics Consulting, Inc., Yorba Linda, CA (USA)); Short, S.A. (ABB Impell Corp., Mission Viejo, CA (USA)); McDonald, J.R. (Texas Tech Univ., Lubbock, TX (USA)); McCann, M.W. Jr. (Benjamin (J.R.) and Associates, Inc., Mountain View, CA (USA)); Murray, R.C. (Lawrence Livermore National Lab., CA (USA)); Hill, J.R. (USDOE Assistant Secretary for Environment, Safety, and He

    1990-06-01

    The Department of Energy (DOE) and the DOE Natural Phenomena Hazards Panel have developed uniform design and evaluation guidelines for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of the guidelines is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. The guidelines apply to both new facilities (design) and existing facilities (evaluation, modification, and upgrading). The intended audience is primarily the civil/structural or mechanical engineers conducting the design or evaluation of DOE facilities. The likelihood of occurrence of natural phenomena hazards at each DOE site has been evaluated by the DOE Natural Phenomena Hazard Program. Probabilistic hazard models are available for earthquake, extreme wind/tornado, and flood. Alternatively, site organizations are encouraged to develop site-specific hazard models utilizing the most recent information and techniques available. In this document, performance goals and natural hazard levels are expressed in probabilistic terms, and design and evaluation procedures are presented in deterministic terms. Design/evaluation procedures conform closely to common standard practices so that the procedures will be easily understood by most engineers. Performance goals are expressed in terms of structure or equipment damage to the extent that: (1) the facility cannot function; (2) the facility would need to be replaced; or (3) personnel are endangered. 82 refs., 12 figs., 18 tabs.

  6. Fluoroscopically guided transforaminal epidural dry needling for lumbar spinal stenosis using a specially designed needle

    Directory of Open Access Journals (Sweden)

    Ahn Kang

    2010-08-01

    Full Text Available Abstract Background This report describes the methodological approach and clinical application of a minimally invasive intervention to treat lumbar spinal stenosis (LSS. Methods Thirty-four patients with LSS underwent fluoroscopically guided transforaminal epidural dry needling using a specially designed flexed Round Needle. The needle was inserted 8-12 cm lateral to the midline at the level of the stenosis and advanced to a position between the anterior side of the facet joint and pedicle up to the outer-third of the pedicle. The needle was advanced medially and backed laterally within a few millimetres along the canal side of the inferior articular process between the facet joint and pedicle. The procedure was completed when a marked reduction in resistance was felt at the tip of the needle. The procedure was performed bilaterally at the level of the stenosis. Results The average follow-up period was 12.9 ± 1.1 months. The visual analogue scale (VAS pain score was reduced from 7.3 ± 2.0 to 4.6 ± 2.5 points, the Oswestry Disability Index (ODI score decreased from 41.4 ± 17.2 to 25.5 ± 12.6% and the average self-rated improvement was 52.6 ± 33.1%. The VAS scores indicated that 14 (41.2% patients reported a "good" to "excellent" treatment response, while 11 (32.4% had a "good" to "excellent" treatment response on the ODI and 22 (64.7% had a "good" to "excellent" treatment response on the self-rated improvement scale. Conclusions These results suggest that fluoroscopically guided transforaminal epidural dry needling is effective for managing LSS.

  7. Conceptual design of a fast-ignition laser fusion reactor based on a dry wall chamber

    Science.gov (United States)

    Ogawa, Y.; Goto, T.; Okano, K.; Asaoka, Y.; Hiwatari, R.; Someya, Y.

    2008-05-01

    The fast ignition is quite attractive for a compact laser fusion reactor, because a sufficiently high pellet gain is available with a small input energy. We designed an inertial fusion reactor based on Fast-ignition Advanced Laser fusion reactor CONcept, called FALCON-D, where a dry wall is employed for a chamber wall. A simple point model shows that the pellet gain G~100 is available with laser energies of 350kJ for implosion, 50kJ for heating. This results in the fusion yield of 40 MJ in one shot. By increasing the repetition rate up to 30 Hz, the fusion power of 1.2 GWth becomes available. Plant system analysis shows the net electric power to be about 0.4 GWe In the fast ignition it is available to employ a low aspect ratio pellet, which is favorable for the stability during the implosion phase. Here the pellet aspect ratio is reduced to be 2 ~ 4, and the optimization of the pulse shape for the implosion laser are carried out by using the 1-D hydrodynamic simulation code ILESTA-1D. A ferritic steel with a tungsten armour is employed for the chamber wall. The feasibility of this dry wall concept is studied from various engineering aspects such as surface melting, physical and chemical sputtering, blistering and exfoliation by helium retention, and thermo-mechanical fatigue, and it is found that blistering and exfoliation due to the helium retention and fatigue failure due to cyclic thermal load are major concerns. The cost analysis shows that the construction cost is moderate but the cost of electricity is slightly expensive.

  8. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  9. Intergenerational Facilities: Designing Intergenerational Space through a Human Development Lens

    OpenAIRE

    Norouzi, Neda

    2016-01-01

    ABSTRACT The built environment can be structured to encourage or discourage social interaction and can have effects on children's cognitive, social, and emotional development as well as effects on elder's health and well-being. Knowing the profound influence of the built environment on elders (Garin, et al., 2014) and children (Bradford, 2012), the design of intergenerational spaces therefore has the potential to influence the interaction between elders and children engaged in intergenerat...

  10. Optimization of the Büchi B-90 spray drying process using central composite design for preparation of solid dispersions.

    Science.gov (United States)

    Gu, Bing; Linehan, Brian; Tseng, Yin-Chao

    2015-08-01

    A central composite design approach was applied to study the effect of polymer concentration, inlet temperature and air flow rate on the spray drying process of the Büchi B-90 nano spray dryer (B-90). Hypromellose acetate succinate-LF was used for the Design of Experiment (DoE) study. Statistically significant models to predict the yield, spray rate, and drying efficiency were generated from the study. The spray drying conditions were optimized according to the models to maximize the yield and efficiency of the process. The models were further validated using a poorly water-soluble investigational compound (BI064) from Boehringer Ingelheim Pharmaceuticals. The polymer/drug ratio ranged from 1/1 to 3/1w/w. The spray dried formulations were amorphous determined by differential scanning calorimetry and X-ray powder diffraction. The particle size of the spray dried formulations was 2-10 μm under polarized light microscopy. All the formulations were physically stable for at least 3h when suspended in an aqueous vehicle composed of 1% methyl cellulose. This study demonstrates that DoE is a useful tool to optimize the spray drying process, and the B-90 can be used to efficiently produce amorphous solid dispersions with a limited quantity of drug substance available during drug discovery stages. Copyright © 2015 Elsevier B.V. All rights reserved.

  11. Siting, design and cost of shallow land burial facilities in northern New England. Volume 1

    International Nuclear Information System (INIS)

    1985-05-01

    This study investigated the technical feasibility and cost of shallow land burial (SLB) as one low-level radioactive waste disposal option for Maine and the northern New England states of Maine, New Hampshire, and Vermont. The results are presented in five chapters addressing the licensing process for an SLB facility, the siting process, the engineering design, the cost of disposal, and the cost of transportation. Chapter 2 reviews the Federal and State licensing processes and requirements for development of an SLB facility. Included in this discussion are the stages in the life cycle of SLB facility. Chapter 3 provides site selection criteria for Maine and presents a proposed site selection methodology. The site selection criteria are defined and the reasoning behind their selection is explained. Chapter 4 discusses SLB trench and facility designs and costs. To accommodate different waste volume scenarios, differently sized facilities are discussed, representing Maine going-it-alone and a northern New England compact. Designs and costs of scenarios including nuclear power plant decommissioning wastes are also discussed. Cost estimates of licensing, facility construction, operation, closure, and post closure care are presented for the different waste volume scenarios. Chapter 5 presents estimates of what it would cost LLW generators to dispose of their waste in a Maine-only or a northern New England shallow land burial facility. The reliability of the estimates and their sensitivity to changes in waste volume are also discussed. Chapter 6 examines transportation costs

  12. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  13. Explore the design style of oriented facility based on user evaluation

    OpenAIRE

    Zhang, Ye; Liu, Yang; Yu, Hui

    2015-01-01

    This paper employs Kansei engineering to analyze the relationship between user preference and the given architectural design scheme. In this study, we first divide architectural styles into seven different categories. Then we classify the key factors in the oriented facility design into 7 types with 39 subcategories. On that basis, we explore which design factor plays main roles in the harmony and unity between the user-oriented type and the given architectural design among seven different ar...

  14. Fermilab Central Computing Facility: Energy conservation report and mechanical systems design optimization and cost analysis study

    Energy Technology Data Exchange (ETDEWEB)

    Krstulovich, S.F.

    1986-11-12

    This report is developed as part of the Fermilab Central Computing Facility Project Title II Design Documentation Update under the provisions of DOE Document 6430.1, Chapter XIII-21, Section 14, paragraph a. As such, it concentrates primarily on HVAC mechanical systems design optimization and cost analysis and should be considered as a supplement to the Title I Design Report date March 1986 wherein energy related issues are discussed pertaining to building envelope and orientation as well as electrical systems design.

  15. Impact of certain safeguards considerations on fuel-cycle facility design

    International Nuclear Information System (INIS)

    Darby, J.L.; de Montmollin, J.M.

    1979-01-01

    Both physical protection and containment/surveillance systems impact plant design and operations. Effective physical protection systems can be systematically designed; work on designing containment/surveillance systems is in progress. Fuel fabrication facility designers need to be cognizant of these safeguards system developments to enable effective implementation of them with as little effect on plant functions as possible. This brief overview provides a general indication of what the impacts of the systems might be, and current thinking on their structure

  16. Design of remote handled process assemblies for the process facility modifications project

    International Nuclear Information System (INIS)

    Smets, J.L.; Ajifu, D.A.

    1987-01-01

    The modular design philosophy for the process facility modification project utilizes an integrated design of components to facilitate operations and maintenance of nuclear fuel reprocessing equipment in a hot cell environment. The utilization of a matrix of remoteable base frames combines with process equipment designed as remote assemblies and sub-assemblies has simplified the overall design. Modularity will allow future flexibility while providing advantages for construction and maintenance in the initial installation

  17. Hospital design Innovation on show at Queensland facility.

    Science.gov (United States)

    Morgan, Kieren; Reading, Megan

    2015-08-01

    In a follow-up to an article on the hospital that first appeared in the autumn 2010 issue of The Australian Hospital Engineer, and was then republished with the help of the magazine. The Institute of Hospital Engineering Australia, and the IFHE in the November 2011 edition of HEJ, principals at architectural firm, Hassell, Kieren Morgan and Megan Reading, explain how the new Gold Coast University Hospital (GCUH) in Southport, Queensland, 'demonstrates how good design can improve delivery of care, as well as staff retention and attraction'.

  18. Maintaining Department of Energy facilities general design criteria

    International Nuclear Information System (INIS)

    Metzler, J.F.

    1985-01-01

    A General Design Criteria (GDC) Planning Board has been established in the Department of Energy to streamline the improvement and maintenance of the GDC Manual. This Planning Board, composed of a membership from field organizations and Headquarters programmatic offices, started work on 15 enhancements to the GDC Manual. One of those enhancements details natural phenomena hazards criteria. In the past year the Planning Board submitted a major recommendation which has been implemented into what is known as the GDC Improvements project. The result of this project pledges to dramatically increase the GDC Manual's utilization and effectiveness

  19. Long-Baseline Neutrino Facility (LBNF) and Deep Underground Neutrino Experiment (DUNE) Conceptual Design Report Volume 3: Long-Baseline Neutrino Facility for DUNE June 24, 2015

    CERN Document Server

    Strait, James; Lundin, Tracy; Willhite, Joshua; Hamernik, Thomas; Papadimitriou, Vaia; Marchionni, Alberto; Kim, Min Jeong; Nessi, Marzio; Montanari, David; Heavey, Anne

    2016-01-01

    This volume of the LBNF/DUNE Conceptual Design Report cover the Long-Baseline Neutrino Facility for DUNE and describes the LBNF Project, which includes design and construction of the beamline at Fermilab, the conventional facilities at both Fermilab and SURF, and the cryostat and cryogenics infrastructure required for the DUNE far detector.

  20. Long-Baseline Neutrino Facility (LBNF) and Deep Underground Neutrino Experiment (DUNE): Conceptual Design Report. Volume 3: Long-Baseline Neutrino Facility for DUNE

    Energy Technology Data Exchange (ETDEWEB)

    Strait, James [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); McCluskey, Elaine [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Lundin, Tracy [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Willhite, Joshua [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Hamernik, Thomas [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Papadimitriou, Vaia [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Marchionni, Alberto [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Kim, Min Jeong [National Inst. of Nuclear Physics (INFN), Frascati (Italy). National Lab. of Frascati (INFN-LNF); Nessi, Marzio [Univ. of Geneva (Switzerland); Montanari, David [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Heavey, Anne [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States)

    2016-01-21

    This volume of the LBNF/DUNE Conceptual Design Report covers the Long-Baseline Neutrino Facility for DUNE and describes the LBNF Project, which includes design and construction of the beamline at Fermilab, the conventional facilities at both Fermilab and SURF, and the cryostat and cryogenics infrastructure required for the DUNE far detector.

  1. Engagement of Facilities Management in Design Stage through BIM: Framework and a Case Study

    Directory of Open Access Journals (Sweden)

    Ying Wang

    2013-01-01

    Full Text Available Considering facilities management (FM at the early design stage could potentially reduce the efforts for maintenance during the operational phase of facilities. Few efforts in construction industry have involved facility managers into the design phase. It was suggested that early adoption of facilities management will contribute to reducing the needs for major repairs and alternations that will otherwise occur at the operational phase. There should be an integrated data source providing information support for the building lifecycle. It is envisaged that Building Information Modelling (BIM would fill the gap by acting as a visual model and a database throughout the building lifecycle. This paper develops a framework of how FM can be considered in design stage through BIM. Based on the framework, the paper explores how BIM will beneficially support FM in the design phase, such as space planning and energy analysis. A case study of using BIM to design facility managers’ travelling path in the maintenance process is presented. The results show that early adoption of FM in design stage with BIM can significantly reduce life cycle costs.

  2. Compensator design for corrector magnet power supply of TPS facility

    International Nuclear Information System (INIS)

    Wong, Y.-S.; Chen, J.-F.; Liu, K.-B.; Liu, C.-Y.; Wang, B.-S.

    2017-01-01

    From 2012 to 2015, Taiwan government has a most important technology project is Taiwan Photon Source (TPS), the total budget of TPS fund to over US300 million. It set up a synchrotron storage ring (electron energy of 3.3 GeV, circumference of 518 m, and low emittance) that provides one of the world's brightest synchrotron sources of x-rays. This study presents a compensator design for corrector magnet power supply to avoid limitations in stabilizing the frequency when the machine output current load is valid. A lead-lag compensator had been built in a full-bridge converter to improve the system bandwidth. Lead-lag compensators influence various disciplines, such as robotics, satellite control, automobile diagnostics, and laser frequency stabilization. These components are important building blocks in analog control systems and can also be used in digital control. A 50V output voltage and 10A output current prototype converter is fabricated in the laboratory. From the experimental results, the effectiveness of the control loop design can be verified from the gain margin and phase margin.

  3. Compensator design for corrector magnet power supply of TPS facility

    Science.gov (United States)

    Wong, Y.-S.; Chen, J.-F.; Liu, K.-B.; Liu, C.-Y.; Wang, B.-S.

    2017-10-01

    From 2012 to 2015, Taiwan government has a most important technology project is Taiwan Photon Source (TPS), the total budget of TPS fund to over US300 million. It set up a synchrotron storage ring (electron energy of 3.3 GeV, circumference of 518 m, and low emittance) that provides one of the world's brightest synchrotron sources of x-rays. This study presents a compensator design for corrector magnet power supply to avoid limitations in stabilizing the frequency when the machine output current load is valid. A lead-lag compensator had been built in a full-bridge converter to improve the system bandwidth. Lead-lag compensators influence various disciplines, such as robotics, satellite control, automobile diagnostics, and laser frequency stabilization. These components are important building blocks in analog control systems and can also be used in digital control. A 50V output voltage and 10A output current prototype converter is fabricated in the laboratory. From the experimental results, the effectiveness of the control loop design can be verified from the gain margin and phase margin.

  4. Design of fixed and mobile PET/CT facilities: the similarities and the challenges

    International Nuclear Information System (INIS)

    Peet, Debbie J.; Pryor, M.

    2008-01-01

    Design of PET/CT facilities present particular challenges for Radiation Protection. The high energy gamma ray emitted from the radionuclides used, the prolonged uptake period with patients within the facility and the relatively high dose rates from those patients result in some shielding being required and a careful consideration of the layout within each unit. This paper will present the approach used for the design of a fixed facility and will present staff dose data demonstrating that the design has resulted in low staff doses. The approach used to design mobile facilities will then be described, and a consideration of the doses received on this type of unit will also be given. The fixed facility was installed into a wooden clad building and was extremely small. The building was shared with other non radiation workers. Walls were constructed from dense concrete blocks and the layout arranged to prevent a direct line of site between the patient and workers at any point apart from the scan room where a lead glass window was used. For the mobile facility lead was used as the shielding material. The basic approach was to maximise the distance between operators and resting patients. Because of weight restrictions and limitation on the dose rate at the scanner defined by the scanner manufacturer, a higher dose constraint had to be adopted for staff on the unit. Additional complications include the mobility of the unit which can be parked adjacent to buildings with a variety of construction materials. Results of whole body monitoring for staff in the fixed facility over 5 years will be presented with the results from the mobile units over the last year. These will demonstrate the difficulties in keeping doses as low as reasonably achievable in the mobile scenario and the importance of designing the facility with staff dose in mind from the outset. (author)

  5. Lead coolant test facility systems design, thermal hydraulic analysis and cost estimate

    Energy Technology Data Exchange (ETDEWEB)

    Khericha, Soli, E-mail: slk2@inel.gov [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Harvego, Edwin; Svoboda, John; Evans, Robert [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Dalling, Ryan [ExxonMobil Gas and Power Marketing, Houston, TX 77069 (United States)

    2012-01-15

    The Idaho National Laboratory prepared a preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic coolant. Based on review of current world lead or lead-bismuth test facilities and research needs listed in the Generation IV Roadmap, five broad areas of requirements were identified as listed below: Bullet Develop and demonstrate feasibility of submerged heat exchanger. Bullet Develop and demonstrate open-lattice flow in electrically heated core. Bullet Develop and demonstrate chemistry control. Bullet Demonstrate safe operation. Bullet Provision for future testing. This paper discusses the preliminary design of systems, thermal hydraulic analysis, and simplified cost estimated. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 4200 Degree-Sign C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.

  6. Biosafety Procedure for Safe Handling of Genetically Modified Plant Materials in Bio Design Facility

    International Nuclear Information System (INIS)

    Zaiton Ahmad; Shuhaimi Shamsudin; Mohamed Najli Mohamed Yasin; Affrida Abu Hassan; Mohd Zaid Hassan; Rusli Ibrahim

    2015-01-01

    Bio Design Facility is the specifically designed glass house for propagation, screening and analysis of high quality plant varieties developed through biotechnology or a combination of nuclear technology and biotechnology. High quality plant varieties especially genetically modified plants (GMO) require a special glass house facility for propagation and screening to isolate them from cross-pollinating with wild type varieties in surrounding ecosystem, and for carrying out evaluation of possible risks of the plants to human, animal and environment before they are proven safe for field trials or commercial release. This facility which was developed under the Ninth Malaysia Plan is classified as the Plant Containment Level 2 and is compliance with the bio safety regulations and guidance for the safe release of GMO according to Malaysian Bio safety Act 2007. Bio Design Facility is fully operational since 2010 and in 2012, it has also been certified as the glass house for post-entry quarantine by The Department of Agriculture. This paper summarizes the bio safety procedure for a safe, controlled and contained growing and evaluation of GMO in Bio Design Facility. This procedure covers the physical (containment and equipment's) and operational (including responsibility, code of practice, growing, decontamination and disposal of plant materials, emergency and contingency plan) aspects of the facility. (author)

  7. Design, fabrication and operation of a biomass fermentation facility. First quarterly report, October 1-December 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    O' Neil, D.J.; Colcord, A.R.; Bery, M.K.; Day, S.W.; Roberts, R.S.; El-Barbary, I.A.; Havlicek, S.C.; Anders, M.E.; Sondhi, D.

    1978-01-01

    The objective of this project is to design, fabricate, and operate a fermentation facility which will demonstrate on a pilot-scale level (3 oven-dry tons (ODT) per day of feedstock) the economic and technical feasibility of producing anhydrous ethyl alcohol from lignocellulosic biomass residues (wood, corn stover, and wheat straw principally). The resultant process development unit (PDU) will be flexibly designed so as to evaluate current and projected unit operations, materials of construction, chemical and enzymatic systems which offer the potential of significant technological and economic breakthroughs in alcohol production from biomass. The principal focus of the project is to generate fuels from biomass. As such, in addition to alcohol which can be used as a transportation fuel, by-products are to be directed where possible to fuel applications. The project consists of two parts: (1) conceptual design, and (2) detailed engineering design. The first quarter's activities have focused on a critical review of several aspects of the conceptual design of the 3 ODT/day PDU, viz.: (1) biomass cost, availability, and characterization; (2) pretreatment processes for lignocellulosic residues; (3) hydrolytic processes (enzymatic and acidic); (4) fermentation processes; (5) alcohol recovery systems; (6) by-product streams utilization; and (7) process economics.

  8. Waste Receiving and Processing Facility, Module 1: Volume 7, Project design criteria

    International Nuclear Information System (INIS)

    1992-03-01

    This Project Design Criteria document for the WRAP facility at the Hanford Site is presented within a systems format. The WRAP Module 1 facility has been categorized into eight (8) engineering systems for design purposes. These systems include: receiving, shipping and storage, nondestructive assay/nondestructive examination (NDA/NDE), waste process, internal transportation, building, heating ventilation and air conditioning (HVAC), process control, and utilities. Within each system section of this document, the system-specific requirements are identified. The scope of the system is defined, the design goals are identified and the functional requirements are detailed

  9. Decontamination and decommissioning criteria for use in design of new plutonium facilities

    International Nuclear Information System (INIS)

    Paschall, R.K.

    1975-01-01

    Decontamination and decommissioning (D and D) criteria were assembled for use in designing new plutonium facilities. These criteria were gathered from literature searches and visits to many plutonium facilities around the country. The recommendations of reports and experienced personnel were used. Since total D and D costs can be millions of dollars, improved designs to facilitate D and D will result in considerable savings in cost and time and will help to leave the site for unrestricted future use after D and D. Finally, better design will reduce hazards and improve safety during the D and D effort

  10. Guidelines for the development of natural phenomena hazards design criteria for surface facilities

    International Nuclear Information System (INIS)

    Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

    1992-01-01

    This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site

  11. Preliminary design of a dedicated synchrotron radiation facility

    International Nuclear Information System (INIS)

    Chasman, R.; Green, G.K.; Rowe, E.M.

    1974-01-01

    An electron storage ring to be used solely as a synchrotron radiation source was designed for a maximum energy of 1.5 GeV, expandable to 2 GeV, and a maximum current of 1 A. High field superconducting magnet wigglers, serving as hard radiation ports, were incorporated into the ring to make available a wide range of wavelengths for simultaneous experiments. The regular lattice consists of a series of small achromatic bends forming the arcs. The wiggler magnets are placed in low-β regions in the center of insertions separating these arcs. The arrangement minimizes the electron emittances and yields high source brightness. Other machine parameters are dictated by experimental requirements and apparatus as well as by cost constraints. (U.S.)

  12. Design and characterisation of a pulsed neutron interrogation facility

    International Nuclear Information System (INIS)

    Favalli, A.; Pedersen, B.

    2007-01-01

    The Joint Research Centre recently obtained a license to operate a new experimental device intended for research in the field of nuclear safeguards. The research projects currently being planned for the new device includes mass determination of fissile materials in matrices and detection of contraband non-nuclear materials. The device incorporates a commercial pulsed neutron generator and a large graphite mantle surrounding the sample cavity. In this configuration, a relatively high thermal neutron flux with a long lifetime is achieved inside the sample cavity. By pulsing the neutron generator, a sample may be interrogated by a pure thermal neutron flux during repeated time periods. The paper reports on the design of the new device and the pulsed fast and thermal neutron source. The thermal neutron flux caused by the neutron generator and the graphite structure has been characterised by foil activation, fission chamber and 3 He proportional counter measurements. (authors)

  13. Design of large sample silicon ingots irradiation facilities using MCNP

    International Nuclear Information System (INIS)

    Abd EL - Latif, S.S.M.

    2012-01-01

    When silicon is irradiated the objective is to produce number of phosphorus atoms in the target sample in order to obtain a given resistivity after the treatment. The resistivity of the sample is decreased by the transmutation of the silicon, by neutrons to phosphorus. Irradiation is carried out by thermal neutrons. The irradiation of silicon ingot large diameter has been carried out in heavy water research reactor since the thermal neutron flux to the fast neutron flux in order of 1000:1. The neutron spectrum is highly thermalized and some of these neutrons can reach the center of the silicon ingot and gives the radial resistivity gradient in accept range. Due to the disadvantages of heavy water research reactor such as tritium generation as a result of the neutron capture by deuterium. The tritium is radioactive emitting beta particles with a half life of 12.3 years so the heavy water research reactor is closed to avoid the intake of bete particles. The new trend in light water research reactor to design a neutron filter from heavy water or graphite to moderate the neutron to offer neutron spectrum like heavy water reactors, and keep the advantages of light water research reactors such as open pool. In this work we try to use graphite, heavy water and light water to design a neutron filter using the MCNP for different silicon ingot diameter.The light water research reactors can irradiate silicon ingot up to 10 inches diameter with accepted radial resistivity gradient (RRG). Graphite is the best filter in case of 10 inch with maximum radial variation (MRV) 7.564%; Light water is the best filter in case of 6 and 8 inch with MRV 2.197% and 4.85% respectively. In case of 6 and 10 inch Heavy water is the second choice.

  14. Staff Technical Position on geological repository operations area underground facility design: Thermal loads

    International Nuclear Information System (INIS)

    Nataraja, M.S.

    1992-12-01

    The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff's position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design

  15. A Tool for the Design of Facilities for the Sustainable Production of Knowledge

    NARCIS (Netherlands)

    Wu, J.

    2005-01-01

    The aim of the study is to develop a ‘design tool’, that is a method to enhance the design and planning of facilities for the sustainable production of new knowledge. More precisely, the objective is to identify a method to support the conception of building complexes related to the long-term

  16. Experimental and Theoretical Progress of Linear Collider Final Focus Design and ATF2 Facility

    CERN Document Server

    Seryi, Andrei; Zimmermann, Frank; Kubo, Kiyoshi; Kuroda, Shigeru; Okugi, Toshiyuki; Tauchi, Toshiaki; Terunuma, Nobuhiro; Urakawa, Junji; White, Glen; Woodley, Mark; Angal-Kalinin, Deepa

    2014-01-01

    In this brief overview we will reflect on the process of the design of the linear collider (LC) final focus (FF) optics, and will also describe the theoretical and experimental efforts on design and practical realisation of a prototype of the LC FF optics implemented in the ATF2 facility at KEK, Japan, presently being commissioned and operated.

  17. Design of 500kW grate fired test facility using CFD

    DEFF Research Database (Denmark)

    Rosendahl, Lasse Aistrup; Kær, Søren Knudsen; Jørgensen, K.

    2005-01-01

    A 500kW vibrating grate fired test facility for solid biomass fuels has been designed using numerical models including CFD. The CFD modelling has focussed on the nozzle layout and flowpatterns in the lower part of the furnace, and the results have established confidence in the chosen design, indi...

  18. Progress towards developing consistent design and evaluation guidelines for DOE facilities subjected to natural phenomena hazards

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Reed, J.W.

    1985-01-01

    Probabilistic definitions of earthquake, wind and tornado natural phenomena hazards for many Department of Energy (DOE) facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. The Department of Energy Natural Phenomena Hazards Panel is now preparing a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment of the facility. Potential effects on facilities of natural phenomena hazards are emphasized in this paper. The philosophy for mitigating these effects to be employed in the design and evaluation guidelines is also presented

  19. Shielding design and performance confirmation of cyclotron facilities

    International Nuclear Information System (INIS)

    Maruyama, Takashi; Kurata, Yasutaka; Kumamoto, Yoshikazu; Inada, Tetsuo; Hashizume, Tadashi

    1978-01-01

    Medical uses of cyclotrons have become active recently in the form of carcinoma therapy and utilization of short-lived radioisotopes. For the shielding design of medical purpose accelerators, already ''Guide-line for shielding calculation for medical purpose high energy accelerator laboratories'' and ''Guide-line for shielding calculation for fast neutron laboratories'' were published. However, the calculation method for cyclotrons is not clear. As for the fundamental concept, the shielding for neutrons generated by the interaction of accelerated particles and the materials used for accelerator construction should be considered as well as the type, energy and intensity of radiations. Also about the activation of air and cooling water, the reactions due to fast and thermal neutrons as well as charged particles should be considered. Then the amount of neutron generation, spectra of neutron energy, angular distribution of neutron, γ ray emitted with neutrons, attenuation of neutron beam and other specific items such as skyshine are described. The specific items include so-called ''groundshine'', 41 Ar generation due to (n-r) reaction, 13 N and 15 O due to fast neutrons and activation of cooling water. Next, the actual results of shielding calculation are described in the case of Institute of Physical and Chemical Research, Institute of Nuclear Study (University of Tokyo), Medical Science Research Laboratory of University of Tokyo and National Institute of Radiological Sciences. (Wakatsuki, Y.)

  20. Solar energy system design for a lobster aquaculture facility

    Energy Technology Data Exchange (ETDEWEB)

    1977-09-30

    In aquaculture, as in most manufacturing processes, the operating cost is greatly dependent upon the cost of energy. The objectives were to: (a) analyze the power requirements for a lobster aquaculture plant, and (b) to evaluate the use of solar energy as a cost reduction measure in plant operation. A flat plate collector system capable of supplying heat alone was compared with a total energy system in which both electrical power and heat were supplied. The flat plate collector was not cost effective because when heat was needed in December, the least amount of heat was available from solar radiation. Therefore, the collector area and cost were prohibitive. However, the total energy system was cost effective when the capital investment was amortized over ten or more years. The optimum solar power plant was designed to provide 100% of the average yearly power demands, or 60% of the December power requirement. This plant would consist of 60,000 square feet of mirror surface (3.5 acres of land for 40% packing density) which would concentrate 1500 to 2000 suns on a receiver mounted on an 85 foot tower. In the tower would be the three storage stoves which would contain the heat required to operate a 343 KWe Brayton gas turbine engine and alternator for 27 hours. Equipment to generate 3 million kw-hr annually will cost an estimated $1.3 million.

  1. Conceptual design of a mirror reactor for a fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Batzer, T.H.; Burleigh, R.C.; Carlson, G.A.; Dexter, W.L.; Hamilton, G.W.; Harvey, A.R.; Hickman, R.G.; Hoffman, M.A.; Hooper, E.B. Jr.; Moir, R.W.; Nelson, R.L.; Pittenger, L.C.; Smith, B.H.; Taylor, C.E.; Werner, R.W.; Wilcox, T.P.

    1975-01-01

    A conceptual design is presented for a small mirror fusion reactor for a Fusion Engineering Research Facility (FERF). The reactor produces 3.4 MW of fusion power and a useful neutron flux of about 10 14 n.cm -2 .s -1 . Superconducting ''yin-yang'' coils are used, and the plasma is sustained by injection of energetic neutral D 0 and T 0 . Conceptual layouts are given for the reactor, its major components, and supporting facilities. (author)

  2. LLL's Quality Assurance Program and the design of specific systems: Tritium Handling Facility

    International Nuclear Information System (INIS)

    Dow, J.P.

    1975-01-01

    Lawrence Livermore Laboratory operates a Tritium Handling Facility for several programs. Besides the tritium work for the weapons program, basic research is conducted on all phases of tritium. Additional work is being conducted for the laser fusion program and the controlled thermonuclear program. The Quality Assurance Program for the tritium facility and how it is being implemented on specific tritium handling systems are described. The program is intended to prevent or mitigate the consequences of accidents by rigidly controlling the design, fabrication, procurement, construction and operation of safety-related critical structures, systems, and components of such facilities. (CH)

  3. Design and operation of a solarheated dry kiln for tropical latitudes

    Science.gov (United States)

    Brian Bond; Omar Espinoza; Philip Araman

    2011-01-01

    Lumber is usually dried to a specific moisture content prior to further manufacturing or use. While lumber can be air-dried, the ambient humidity in most localities prevents the lumber from reaching the moisture content necessary for dimensional stability and use, especially for interior use. Solar kilns are an inexpensive alternative to conventional steam-heated kilns...

  4. A proposed regulatory policy statement on human factors requirements in the design and operation of Canadian nuclear facilities

    International Nuclear Information System (INIS)

    1986-10-01

    With the increasing complexity of new nuclear facilities and the extent to which automation is being applied, it is essential that the staff who operate a facility be considered as integral components in the design and safety analyses. This policy statement is proposed to indicate those areas of facility design and operation where the role of the human operator must be especially examined

  5. Ethanol Production from Biomass: Large Scale Facility Design Project

    Energy Technology Data Exchange (ETDEWEB)

    Berson, R. Eric [Univ. of Louisville, KY (United States)

    2009-10-29

    High solids processing of biomass slurries provides the following benefits: maximized product concentration in the fermentable sugar stream, reduced water usage, and reduced reactor size. However, high solids processing poses mixing and heat transfer problems above about 15% for pretreated corn stover solids due to their high viscosities. Also, highly viscous slurries require high power consumption in conventional stirred tanks since they must be run at high rotational speeds to maintain proper mixing. An 8 liter scraped surface bio-reactor (SSBR) is employed here that is designed to efficiently handle high solids loadings for enzymatic saccharification of pretreated corn stover (PCS) while maintaining power requirements on the order of low viscous liquids in conventional stirred tanks. Saccharification of biomass exhibit slow reaction rates and incomplete conversion, which may be attributed to enzyme deactivation and loss of activity due to a variety of mechanisms. Enzyme deactivation is classified into two categories here: one, deactivation due to enzyme-substrate interactions and two, deactivation due to all other factors that are grouped together and termed “non-specific” deactivation. A study was conducted to investigate the relative extents of “non-specific” deactivation and deactivation due to “enzyme-substrate interactions” and a model was developed that describes the kinetics of cellulose hydrolysis by considering the observed deactivation effects. Enzyme substrate interactions had a much more significant effect on overall deactivation with a deactivation rate constant about 20X higher than the non-specific deactivation rate constant (0.35 h-1 vs 0.018 h-1). The model is well validated by the experimental data and predicts complete conversion of cellulose within 30 hours in the absence of enzyme substrate interactions.

  6. A strategic approach to the conceptual design of complex radwaste facilities

    International Nuclear Information System (INIS)

    Mackay, Stewart; Scott Dam, A.; Holmes, Robert G.G.

    1992-01-01

    The design of radwaste treatment facilities is often complicated by the variety of waste types being treated. Further uncertainties over their composition and final waste form specifications can make the normal conceptual design phase difficult and unreliable. This paper describes the strategic planning necessary to define the facility functions and the process to prepare a Functional Design Criteria. The paper shows clearly, that for complex waste management problems, it is vital to consider and resolve uncertainties by means of a strategic plan before embarking on conceptual design. The paper shows an approach to preparation of design criteria using functional analysis. The paper provides examples where these methods were and are being used, both in the U.K. and the U.S. Strategic plans and functional criteria can be used as a basis for conceptual design which then provides a more meaningful basis for detailed technology selection during the detailed design process. The paper discusses experiences and lessons learned in the planning process. This process is widely applicable to a number of complex waste treatment facilities being planned and developed to process wastes generated at government facilities. (author)

  7. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    International Nuclear Information System (INIS)

    Christensen, Boyd D.

    2010-01-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  8. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Christensen

    2010-02-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  9. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Christensen

    2010-05-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  10. Design of experiment characterization of microneedle fabrication processes based on dry silicon etching

    Science.gov (United States)

    Held, J.; Gaspar, J.; Ruther, P.; Hagner, M.; Cismak, A.; Heilmann, A.; Paul, O.

    2010-02-01

    This paper reports on the characterization of dry etching-based processes for the fabrication of silicon microneedles using a design of experiment (DoE) approach. The possibility of using such microneedles as protruding microelectrodes able to electroporate adherently growing cells and record intracellular potentials motivates the systematic analysis of the influence of etching parameters on the needle shape. Two processes are characterized: a fully isotropic etch process and a three-step etching approach. In the first case, the shape of the microneedles is defined by a single etch step. For the stepped method, the structures are realized using the following sequence: a first, isotropic step defines the tip; this is followed by anisotropic etching that increases the height of the needle; a final isotropic procedure thins the microneedle and sharpens its tip. From the various process parameters tested, it is concluded that the isotropic fabrication is influenced mostly by four process parameters, whereas six parameters dominantly govern the outcome of the stepped etching technique. The dependence of the needle shape on the etch mask diameter is also investigated. Microneedles with diameters down to the sub-micrometer range and heights below 10 µm are obtained. The experimental design is performed using the D-optimal method. The resulting geometry, i.e. heights, diameters and radii of curvature measured at different positions, is extracted from scanning electron micrographs of needle cross-sections obtained from cuts by focused ion beam. The process parameters are used as inputs and the geometry features of the microneedles as outputs for the analysis of the process.

  11. Design of experiment characterization of microneedle fabrication processes based on dry silicon etching

    International Nuclear Information System (INIS)

    Held, J; Gaspar, J; Ruther, P; Paul, O; Hagner, M; Cismak, A; Heilmann, A

    2010-01-01

    This paper reports on the characterization of dry etching-based processes for the fabrication of silicon microneedles using a design of experiment (DoE) approach. The possibility of using such microneedles as protruding microelectrodes able to electroporate adherently growing cells and record intracellular potentials motivates the systematic analysis of the influence of etching parameters on the needle shape. Two processes are characterized: a fully isotropic etch process and a three-step etching approach. In the first case, the shape of the microneedles is defined by a single etch step. For the stepped method, the structures are realized using the following sequence: a first, isotropic step defines the tip; this is followed by anisotropic etching that increases the height of the needle; a final isotropic procedure thins the microneedle and sharpens its tip. From the various process parameters tested, it is concluded that the isotropic fabrication is influenced mostly by four process parameters, whereas six parameters dominantly govern the outcome of the stepped etching technique. The dependence of the needle shape on the etch mask diameter is also investigated. Microneedles with diameters down to the sub-micrometer range and heights below 10 µm are obtained. The experimental design is performed using the D-optimal method. The resulting geometry, i.e. heights, diameters and radii of curvature measured at different positions, is extracted from scanning electron micrographs of needle cross-sections obtained from cuts by focused ion beam. The process parameters are used as inputs and the geometry features of the microneedles as outputs for the analysis of the process.

  12. Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.

  13. Optimal capacity design of LID facility for conserving natural water cycle and its sensitivity analysis

    Science.gov (United States)

    Lee, O.; Choi, J.; Lee, J.; Kim, S.

    2017-12-01

    Since the 20th century, urbanization has resulted in increased impermeable land surface and reduced infiltration capacity in catchment scale. Especially, when agriculture area or forest area would be developed into urban area, it can cause more runoff in the same climate condition. Such urbanization causes problems such as changes in hydrological cycle and ecosystem disturbance. Various methods have been proposed worldwide to reduce the impact of such urbanization. Among the various strategies, the low-impact development is a development strategy that aims to return to pre-development state by minimizing the change of the hydrological cycle due to urbanization. In this strategy, the infiltration and/or surface storage of stormwater runoff can be increased through the installation of various facilities. In this study, a facility capacity design strategy is proposed to return into the natural water cycle through the installation of various LID facilities. This is accomplished by determining the optimal LID facility design capacity through which flow duration curves remain the same before and after urban development. For this purpose, EPA-SWMM is constructed with a part of Busan Metropolitan City Noksan Industrial Complex as a virtual processing area. Under the various land-use scenarios, the optimum design capacity of various LID facilities capable of retaining the flow duration curve before and after development is determined. In addition, the sensitivity of the optimal design capacity of LID facilities is analyzed according to the design specifications of various LID facilities, the local rainfall characteristics, and the size of the treatment area. Acknowledgement This research was supported by a grant (2016000200002) from Public Welfare Technology Development Program funded by Ministry of Environment of Korean government.

  14. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    Energy Technology Data Exchange (ETDEWEB)

    Soli T. Khericha

    2006-09-01

    This report presents preliminary technical and functional requirements (T&FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T&FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420oC. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation.

  15. Optimising mechanical strength and bulk density of dry ceramic bodies through mixture design

    Directory of Open Access Journals (Sweden)

    Correia, S. L.

    2005-02-01

    Full Text Available In industrial practice, it is desirable to be able to predict, in an expeditious way, what the effects of a change in raw materials or the proportions thereof might be in the various processing steps towards the final product. When the property of interest is basically determined by the combination (or mixture of raw materials, an optimisation methodology specific to the design of mixture experiments can be successfully used. In the present study, dry bending strength and bulk density were selected as the properties to model, given the simplicity of their experimental determination and because they are frequently used as quality control parameter in the development and manufacture stages of floor and wall ceramic tiles. Ten formulations of three raw materials (a clay mixture, potash feldspar and quartz sand were processed in the laboratory under fixed conditions, similar to those used in the ceramics industry, and characterised. The use of this methodology enabled the calculation of valid regression models (equations relating dry bending strength and bulk density with the contents, in the starting mixture, of the particular raw materials used.

    En el trabajo industrial es deseable poder predecir de manera efectiva, los efectos que los cambios en las materias primas o en sus proporciones pueden ejercer sobre las variables del proceso y como estos afectan al producto final. Cuando la propiedad de interés depende preferentemente de la mezcla de las materias primas, una metodología específica de optimización para el diseño de los experimentos de mezclas puede ser empleada con éxito. En este trabajo, la resistencia mecánica en seco y la densidad se emplearon como los parámetros de control en el desarrollo y producción de azulejos cerámicos para pavimento y revestimiento. Diez formulaciones a partir de tres materias primas ( una mezcla de arcilla, feldespato potásico y arena de cuarzo fueron procesadas en el laboratorio bajo

  16. U.S. Environmental Protection Agency Clear Air Act notice of construction for the spent nuclear fuel project - Cold Vacuum Drying Facility, project W-441

    International Nuclear Information System (INIS)

    Turnbaugh, J.E.

    1996-01-01

    This document provides information regarding the source and the estimated quantity of potential airborne radionuclide emissions resulting from the operation of the Cold Vacuum Drying (CVD) Facility. The construction of the CVD Facility is scheduled to commence on or about December 1996, and will be completed when the process begins operation. This document serves as a Notice of Construction (NOC) pursuant to the requirements of 40 Code of Federal Regulations (CFR) 61 for the CVD Facility. About 80 percent of the U.S. Department of Energy's spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters, while the SNF in the K East Basin is in open canisters, which allow release of corrosion products to the K East Basin water. Storage of the current inventory in the K Basins was originally intended to be on an as-needed basis to sustain operation of the N Reactor while the Plutonium-Uranium Extraction (PUREX) Plant was refurbished and restarted. The decision in December 1992 to deactivate the PURF-X Plant left approximately 2,100 MT (2,300 tons) of uranium as part of the N Reactor SNF in the K Basins with no means for near-term removal and processing. The CVD Facility will be constructed in the 100 Area northwest of the 190 K West Building, which is in close proximity to the K East and K West Basins (Figures 1 and 08572). The CVD Facility will consist of five processing bays, with four of the bays fully equipped with processing equipment and the fifth bay configured as an open spare bay. The CVD Facility will have a support area consisting of a control room, change rooms, and other functions required to support operations

  17. Development of a microparticle-based dry powder inhalation formulation of ciprofloxacin hydrochloride applying the quality by design approach

    Directory of Open Access Journals (Sweden)

    Karimi K

    2016-10-01

    Full Text Available Keyhaneh Karimi, Edina Pallagi, Piroska Szabó-Révész, Ildikó Csóka, Rita Ambrus Faculty of Pharmacy, Institute of Pharmaceutical Technology and Regulatory Affairs, University of Szeged, Szeged, Hungary Abstract: Pulmonary drug delivery of ciprofloxacin hydrochloride offers effective local antibacterial activity and convenience of easy application. Spray drying is a trustworthy technique for the production of ciprofloxacin hydrochloride microparticles. Quality by design (QbD, an up-to-date regulatory-based quality management method, was used to predict the final quality of the product. According to the QbD-based theoretical preliminary parameter ranking and priority classification, dry powder inhalation formulation tests were successfully performed in practice. When focusing on the critical parameters, the practical development was more effective and was in correlation with our previous findings. Spray drying produced spherical microparticles. The dry powder formulations prepared were examined by particle size analysis, scanning electron microscopy, Fourier-transform infrared spectroscopy, X-ray powder diffraction, differential scanning calorimetry, and in vitro drug release and aerodynamic particle size analyses were also performed. These formulations showed an appropriate particle size ranging between 2 and 4 µm and displayed an enhanced aerosol performance with fine particle fraction up to 80%. Keywords: antibiotic, carrier-free formulation, quality by design, aerodynamic evaluation, dry powder for inhalation

  18. Design Basis Provisions for New and Existing Nuclear Power Plants and Nuclear Fuel Cycle Facilities in India

    International Nuclear Information System (INIS)

    Soni, R.S.

    2013-01-01

    India has 3-Stage Nuclear Power Program. • Various facilities under design, construction or operation. • Design Basis Knowledge Management (DBKM) is an important and challenging task. • Design Basis Knowledge contributes towards: - Safe operation of running plants; - Design and construction of new facilities; - Addresses issues related to future decommissioning activities

  19. A conceptual subsurface facility design for a high-level nuclear waste repository at Yucca Mountain

    International Nuclear Information System (INIS)

    McKenzie, D.G., III; Bhattacharyya, K.K.; Segrest, A.M.

    1996-01-01

    The US Department of Energy is responsible for the design, construction, operation and closure of a repository in which to permanently dispose of the nation's high level nuclear waste. In addition to the objective of safely isolating the waste inventory, the repository must provide a safe working environment for its workforce, and protect the public. The conceptual design for this facility is currently being developed. Tunnel Boring Machine will be used to excavate 228 kilometers of tunneling to construct the facility over a 30 year period. The excavation operations will be physically separated from the waste emplacement operations, and each operation will have its own dedicated ventilation system. The facility is being designed to remain open for 150 years

  20. Design of a Facility to Test the Advanced Stirling Radioisotope Generator Engineering Unit

    Science.gov (United States)

    Lewandowski, Edward J.; Schreiber, Jeffrey G.; Oriti, Salvatore M.; Meer, David W.; Brace, Michael H.; Dugala, Gina

    2009-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) is being considered to power deep space missions. An engineering unit, the ASRG-EU, was designed and fabricated by Lockheed Martin under contract to the Department of Energy. This unit is currently on an extended operation test at NASA Glenn Research Center to generate performance data and validate the life and reliability predictions for the generator and the Stirling convertors. A special test facility was designed and built for testing the ASRG-EU. Details of the test facility design are discussed. The facility can operate the convertors under AC bus control or with the ASRG-EU controller. It can regulate input thermal power in either a fixed temperature or fixed power mode. An enclosure circulates cooled air around the ASRG-EU to remove heat rejected from the ASRG-EU by convection. A custom monitoring and data acquisition system supports the test. Various safety features, which allow 2417 unattended operation, are discussed.

  1. Conceptual designs for waste quality checking facilities for low level and intermediate level radioactive wastes and hazardous waste

    International Nuclear Information System (INIS)

    Driver, S.; Griffiths, M.; Leonard, C.D.; Smith, D.L.G.

    1992-01-01

    This report summarises work carried out on the design of facilities for the quality checking of Intermediate and Low Level Radioactive Waste and Hazardous Waste. The procedures used for the quality checking of these categories of waste are summarised. Three building options are considered: a separate LLW facility, a combined facility for LLW and HW and a Waste Quality Checking Facility for the three categories of waste. Budget Cost Estimates for the three facilities are given based on 1991 prices. (author)

  2. Savannah River Plant, Project 8980: Engineering and design history of power and electrical facilities. Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    1957-01-01

    This section of the Engineering-and Design History presents a comprehensive account of the planning and extensive evaluation of the problems involved in reaching basic decisions for the design and installation of power facilities at the Savannah River Plant. The problems were complicated by the urgency of Pro. viding early start-up of facilities at a time when critical material shortages were acute, combined with basic requirements for reliable operation and unusual degrees of flexibility to meet a variety of production demands. Part I describes in detail the steam and water facilities, alternative schemes, and other considerations which were evaluated as a prelude to the final design of equipment and facilities. Included are discussions relating to steam boiler installations, electric power generation, diesel engine plants, mater supply for cooling, process and domestic use, and the numerous water treatment procedures employed for specific application. A comprehensive description of the development and design of electric power facilities is presented in Part II of this volume.

  3. Human engineering considerations in the design of New Virginia Power Radwaste facilities

    International Nuclear Information System (INIS)

    Bankley, A.V.; Morris, L.L.; Lippard, D.W.

    1988-01-01

    Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

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

    Science.gov (United States)

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

    2018-01-01

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

  5. The Practice of Sustainable Facilities Management: Design Sentiments and the Knowledge Chasm

    Directory of Open Access Journals (Sweden)

    Abbas Elmualim

    2009-12-01

    Full Text Available The construction industry with its nature of project delivery is very fragmented in terms of the various processes that encompass design, construction, facilities and assets management. Facilities managers are in the forefront of delivering sustainable assets management and hence further the venture for mitigation and adaptation to climate change. A questionnaire survey was conducted to establish perceptions, level of commitment and knowledge chasm in practising sustainable facilities management (FM. This has significant implications for sustainable design management, especially in a fragmented industry. The majority of questionnaire respondents indicated the importance of sustainability for their organization. Many of them stated that they reported on sustainability as part of their organization annual reporting with energy efficiency, recycling and waste reduction as the main concern for them. The overwhelming barrier for implementing sound, sustainable FM is the lack of consensual understanding and focus of individuals and organizations about sustainability. There is a knowledge chasm regarding practical information on delivering sustainable FM. Sustainability information asymmetry in design, construction and FM processes render any sustainable design as a sentiment and mere design aspiration. Skills and training provision, traditionally offered separately to designers and facilities managers, needs to be re-evaluated. Sustainability education and training should be developed to provide effective structures and processes to apply sustainability throughout the construction and FM industries coherently and as common practice. Published in the Journal AEDM - Volume 5, Numbers 1-2, 2009 , pp. 91-102(12

  6. National Ignition Facility subsystem design requirements optics assembly building (OAB) SSDR 1.2.2.3

    International Nuclear Information System (INIS)

    Kempel, P.; Hands, J.

    1996-01-01

    This Subsystem Design Requirement (SSDR) document establishes the performance, design, and verification requirements 'for the conventional building systems and subsystems of the Optics Assembly Building (OAB). These building system requirements are associated with housing and supporting the operational flow of personnel and materials throughout the OAB for preparing and repairing optical and mechanical components used in the National Ignition Facility (NIF) Laser and Target Building (LTAB). This SSDR addresses the following subsystems associated with the OAB: * Structural systems for the building spaces and operational-support equipment and building- support equipment. * Architectural building features associated with housing the space, operational cleanliness, and functional operation of the facility. * Heating, Ventilating, and Air Conditioning (HVAC) systems for maintaining a clean and thermally stable ambient environment within the facility. * Plumbing systems that provide potable water and sanitary facilities for the occupants and stormwater drainage for transporting rainwater. * Fire Protection systems that guard against fire damage to the facility and its contents. * Material handling equipment for transferring optical assemblies and other materials within building areas and to the LTAB. * Mechanical process piping systems for liquids and gases that provide cooling, cleaning, and other service to optical and mechanical components. * Electrical power and grounding systems that provide service to the building and equipment, including lighting distribution and communications systems for the facilities. * Instrumentation and control systems that ensure the safe operation of conventional facilities systems, such as those listed above. Generic design criteria, such as siting data, seismic requirements, utility availability, and other information that contributes to the OAB design, are not addressed in this document

  7. Code of practice for the design and safe operation of non-medical irradiation facilities (1988)

    International Nuclear Information System (INIS)

    1988-01-01

    This Code establishes requirements for the design and operation of irradiation facilities which use X-rays, electrons or gamma radiation for non-medical purposes such as the sterilisation of therapeutic goods. These requirements aim to ensure that exposure of workers and members of the public to ionizing and non-ionizing radiation as well as to noxious gases and radioactive contamination of the environment and facilities are controlled through the design of engineering safety features, approved administrative controls and appropriate radiation monitoring [fr

  8. Staff technical position on regulatory considerations in the design and construction of the exploratory shaft facility

    International Nuclear Information System (INIS)

    Gupta, D.; Peshel, J.; Bunting, J.

    1991-07-01

    The staff of the US Nuclear Regulatory Commission has prepared this staff technical position for the purpose of compiling and further clarifying previous staff positions on regulatory considerations in the design and construction of the exploratory shaft facility (ESF). (The US Department of Energy (DOE) now refers to the ESF as the ''exploratory studies facility.'' DOE's change in terminology does not affect the positions taken in this guidance.) This document lists the key regulations in 10 CFR Part 60 that should be considered in the design and construction of the ESF and presents the staff position statements and corresponding discussions. 13 refs., 1 fig

  9. Feasibility study for Zaporozhye Nuclear Power Plant spent fuel dry storage facility in Ukraine. Export trade information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    This document reports the results of a Feasibility Study sponsored by a TDA grant to Zaporozhye Nuclear Power Plant (ZNPP) in Ukraine to study the construction of storage facilities for spent nuclear fuel. It provides pertinent information to U.S. companies interested in marketing spent fuel storage technology and related business to countries of the former Soviet Union or Eastern Europe.

  10. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    International Nuclear Information System (INIS)

    2009-01-01

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

  11. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  12. Utilizing integrated facility design to improve the quality of a pediatric ambulatory surgery center.

    Science.gov (United States)

    Pelly, Nicole; Zeallear, Brian; Reed, Mark; Martin, Lynn

    2013-07-01

    The aim was to use Integrated Facility Design (IFD) to design a surgery center that enhances the delivery of health care by developing processes that provide highly efficient patient, family, and provider flows while adding value and utilizing costly resources effectively. Integrated Facility Design is an adaptation of the Toyota 3P (Production, Preparation, Process) Program. The goal of IFD is to accelerate development time and lower start-up costs. The use of IFD produced a savings of $30 million in project costs and enabled a completion date 3.5 months ahead of schedule. The designed patient flow processes resulted in dramatic improvements in patient, family, and provider throughput. The use of IFD in the design of a pediatric ambulatory clinic and surgery resulted in significant cost savings and improved clinical efficiency. © 2013 John Wiley & Sons Ltd.

  13. performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, Renato L. A.; Filho, Josélio S. M., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear. Divisão de Normas e Segurança Física; Fontes, Gladson S.; Fiel, J.C.B., E-mail: gsfontes@hotmail.com, E-mail: fiel@ime.eb.br [Instituto Militar de Engenharia (SE-7/IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

    2017-07-01

    This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

  14. Analysis of a shield design for a DT neutron generator test facility.

    Science.gov (United States)

    Chichester, D L; Pierce, G D

    2007-10-01

    Independent numerical simulations have been performed using the MCNP5 and SCALE5 radiation transport codes to evaluate the effectiveness of a concrete facility designed to shield personnel from neutron radiation emitted from DT neutron generators. The analysis considered radiation source terms of 14.1 MeV monoenergetic neutrons located at three discrete locations within the two test vaults in the facility, calculating neutron and photon dose rates at 44 locations around the facility using both codes. In addition, dose rate contours were established throughout the facility using the MCNP5 mesh tally feature. Neutron dose rates calculated outside of the facility are predicted to be below 0.01 mrem/h at all locations when all neutron generator source terms are operating within the facility. Similarly, the neutron dose rate in one empty test vault when the adjacent test vault is being utilized is also less then 0.01 mrem/h. For most calculation locations outside the facility the photon dose rates were less then the neutron dose rates by a factor of 10 or more.

  15. Fast freeze-drying cycle design and optimization using a PAT based on the measurement of product temperature.

    Science.gov (United States)

    Bosca, Serena; Barresi, Antonello A; Fissore, Davide

    2013-10-01

    This paper is focused on the use of an innovative Process Analytical Technology for the fast design and optimization of freeze-drying cycles for pharmaceuticals. The tool is based on a soft-sensor, a device that uses the experimental measure of product temperature during freeze-drying, a mathematical model of the process, and the Extended Kalman Filter algorithm to estimate the sublimation flux, the residual amount of ice in the vial, and some model parameters (heat and mass transfer coefficients). The accuracy of the estimations provided by the soft-sensor has been shown using as test case aqueous solutions containing different excipients (sucrose, polyvinylpyrrolidone), processed at various operating conditions, pointing out that the soft-sensor allows a fast estimation of model parameters and product dynamics without involving expensive hardware or time consuming analysis. The possibility of using the soft-sensor to calculate in-line (or off-line) the design space of the primary drying phase is here presented and discussed. Results evidences that by this way, it is possible to identify the values of the heating fluid temperature that maintain product temperature below the limit value, as well as the operating conditions that maximize the sublimation flux. Various experiments have been carried out to test the effectiveness of the proposed approach for a fast design of the cycle, evidencing that drying time can be significantly reduced, without impairing product quality. Copyright © 2013 Elsevier B.V. All rights reserved.

  16. Optimization of Chitosan Microspheres Spray Drying via 32 Full Factorial Design

    Directory of Open Access Journals (Sweden)

    Katsarov Plamen D.

    2017-09-01

    Full Text Available Background: Generally, the preparation of spray-dried microspheres is strongly affected by the process parameters. Particle size and production yield are mainly influenced by the spraying solution concentration and the pump rate of the spray dryer.

  17. Conceptual design for the Waste Receiving And Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. This volume provides the detailed cost estimate for the WRAP 2A facility. Included in this volume is the project construction schedule

  18. Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

  19. DESIGN OF FILL AND FINISH FACILITY FOR ACTIVE PHARMACEUTICAL INGREDIENTS (API

    Directory of Open Access Journals (Sweden)

    NUUR LAILA KHAIRUDDIN

    2016-08-01

    Full Text Available Fill and finish operations continue to be one of the most heavily outsourced activities in the biopharmaceutical manufacturing market today. There are a few aspects that need to be consider in outsource activities like logistic, storage condition, facility certification and audit as regulations and standards which the manufacturer should adhere. Risk would be greater and extra care should be taken when outsource from foreign fill and finish facility. Thus, the internal aseptic fill and finish facility with audit checklist will help to minimize the risk during logistic and storage and also minimize the cost for outsource fill and finish facility. The data collections are through survey and conceptual design with simulation as the execution part.

  20. SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

    International Nuclear Information System (INIS)

    Achilli, A.; Congiu, C.; Ferri, R.; Bianchi, F.; Meloni, P.; Grgic, D.; Dzodzo, M.

    2012-01-01

    An Italian MSE R and D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. IRIS is a modular, medium size, advanced, integral PWR, developed by an international consortium of utilities, industries, research centres and universities. SPES3 simulates the primary, secondary and containment systems of IRIS, with 1:100 volume scale, full elevation and prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to the design of the facility to identify criticalities and weak points in the reactor simulation. FER, at Zagreb University, performed the IRIS reactor analyses with the RELAP5 and GOTHIC coupled codes. The comparison between IRIS and SPES3 simulation results led to a simulation-design feedback process with step-by-step modifications of the facility design, up to the final configuration. For this, a series of sensitivity cases was run to investigate specific aspects affecting the trend of the main parameters of the plant, as the containment pressure and EHRS removed power, to limit fuel clad temperature excursions during accidental transients. This paper summarizes the sensitivity analyses on the containment system that allowed to review the SPES3 facility design and confirm its capability to appropriately simulate the IRIS plant.

  1. SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

    Directory of Open Access Journals (Sweden)

    Andrea Achilli

    2012-01-01

    Full Text Available An Italian MSE R&D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. IRIS is a modular, medium size, advanced, integral PWR, developed by an international consortium of utilities, industries, research centres and universities. SPES3 simulates the primary, secondary and containment systems of IRIS, with 1:100 volume scale, full elevation and prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to the design of the facility to identify criticalities and weak points in the reactor simulation. FER, at Zagreb University, performed the IRIS reactor analyses with the RELAP5 and GOTHIC coupled codes. The comparison between IRIS and SPES3 simulation results led to a simulation-design feedback process with step-by-step modifications of the facility design, up to the final configuration. For this, a series of sensitivity cases was run to investigate specific aspects affecting the trend of the main parameters of the plant, as the containment pressure and EHRS removed power, to limit fuel clad temperature excursions during accidental transients. This paper summarizes the sensitivity analyses on the containment system that allowed to review the SPES3 facility design and confirm its capability to appropriately simulate the IRIS plant.

  2. Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Timothy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-09-01

    At Sandia National Laboratories in New Mexico (SNL/NM), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/NM applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

  3. Conceptual design for the Waste Receiving and Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This is part of a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at the Hanford Reservation. The mission of the facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluent treatment facilities, thermal treatment facility ash, other WRAP modules, and other miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume III is a compilation of the outline specifications that will form the basis for development of the Title design construction specifications. This volume contains abbreviated CSI outline specifications for equipment as well as non-equipment related construction and material items. For process and mechanical equipment, data sheets are provided with the specifications which indicate the equipment overall design parameters. This volume also includes a major equipment list

  4. The FAO/IAEA interactive spreadsheet for design and operation of insect mass rearing facilities

    International Nuclear Information System (INIS)

    Caceres, Carlos; Rendon, Pedro

    2006-01-01

    An electronic spreadsheet is described which helps users to design, equip and operate facilities for the mass rearing of insects for use in insect pest control programmes integrating the sterile insect technique. The spreadsheet was designed based on experience accumulated in the mass rearing of the Mediterranean fruit fly, Ceratitis capitata (Wiedemann), using genetic sexing strains based on a temperature sensitive lethal (tsl) mutation. The spreadsheet takes into account the biological, production, and quality control parameters of the species to be mass reared, as well as the diets and equipment required. All this information is incorporated into the spreadsheet for user-friendly calculation of the main components involved in facility design and operation. Outputs of the spreadsheet include size of the different rearing areas, rearing equipment, volumes of diet ingredients, other consumables, as well as personnel requirements. By adding cost factors to these components, the spreadsheet can estimate the costs of facility construction, equipment, and operation. All the output parameters can be easily generated by simply entering the target number of sterile insects required per week. For other insect species, the biological and production characteristics need to be defined and inputted accordingly to obtain outputs relevant to these species. This spreadsheet, available under http://www-naweb.iaea.org/nafa/ipc/index.html, is a powerful tool for project and facility managers as it can be used to estimate facility cost, production cost, and production projections under different rearing efficiency scenarios. (author)

  5. Conceptual design for the Waste Receiving and Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This is part of a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at Hanford Reservation. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated at WRAP Module 2A include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluenttreatment facilities, thermal treatment facility ash, other WRAP modules, and other miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume V, provides a comprehensive conceptual design level narrative description of the process, utility, ventilation, and plant control systems. The feeds and throughputs, design requirements, and basis for process selection are provided, as appropriate. Key DOE/WHC criteria and reference drawings are delineated

  6. Spray dried amikacin powder for inhalation in cystic fibrosis patients: a quality by design approach for product construction.

    Science.gov (United States)

    Belotti, Silvia; Rossi, Alessandra; Colombo, Paolo; Bettini, Ruggero; Rekkas, Dimitrios; Politis, Stavros; Colombo, Gaia; Balducci, Anna Giulia; Buttini, Francesca

    2014-08-25

    An amikacin product for convenient and compliant inhalation in cystic fibrosis patients was constructed by spray-drying in order to produce powders of pure drug having high respirability and flowability. An experimental design was applied as a statistical tool for the characterization of amikacin spray drying process, through the establishment of mathematical relationships between six Critical Quality Attributes (CQAs) of the finished product and five Critical Process Parameters (CPPs). The surface-active excipient, PEG-32 stearate, studied for particle engineering, in general did not benefit the CQAs of the spray dried powders for inhalation. The spray drying feed solution required the inclusion of 10% (v/v) ethanol in order to reach the desired aerodynamic performance of powders. All desirable function solutions indicated that the favourable concentration of amikacin in the feed solution had to be kept at 1% w/v level. It was found that when the feed rate of the sprayed solution was raised, an increase in the drying temperature to the maximum value (160 °C) was required to maintain good powder respirability. Finally, the increase in drying temperature always led to an evident increase in emitted dose (ED) without affecting the desirable fine particle dose (FPD) values. The application of the experimental design enabled us to obtain amikacin powders with both ED and FPD, well above the regulatory and scientific references. The finished product contained only the active ingredient, which keeps low the mass to inhale for dose requirement. Copyright © 2014 Elsevier B.V. All rights reserved.

  7. Design, construction and performance of the current lead test facility CuLTKa

    Science.gov (United States)

    Richter, T.; Bobien, S.; Fietz, W. H.; Heiduk, M.; Heller, R.; Hollik, M.; Lange, C.; Lietzow, R.; Rohr, P.

    2017-09-01

    The Karlsruhe Institute of Technology (KIT) has a longtime experience in the development of High Temperature Superconductor (HTS) Current Leads (CLs) for high currents leading to several contracts with national and international partners. Within these contracts series production and cold acceptance tests of such CLs were required. The cold test of a large number of CLs requires the availability of a flexible facility which allows fast and reproducible testing. With the Current Lead Test Facility Karlsruhe (CuLTKa) a versatile and flexible test bed for CLs was designed and constructed. The facility consists of five cryostats including two test boxes and is directly connected by a transfer line to a refrigerator with a capacity of 2 kW at 4.4 K. The refrigerator supplies supercritical helium at two different temperature levels simultaneously. Each of the two test cryostats can be equipped with a pair of CLs which is short-circuited at the low temperature level via a superconducting bus bar. For current tests a power supply can provide DC currents up to 30 kA. If required, the facility design offers the potential of withstanding high voltages of up to 50 kV on the test objects. The commissioning of the facility started in July 2014. In total a series of acceptance tests of the CLs for the Japanese JT-60SA will be carried out until second half of 2017 to qualify six CLs with a current of 26 kA and 20 CLs with a current of 20 kA. In the meantime, six CLs@26 kA and 16 CLs@20 kA have been tested in CuLTKa which demonstrates the very effective operation of the facility. This paper describes the setup of the facility from cryogenic, electrical and process control point of view and will highlight the design of particular technical aspects. Furthermore, an overview of the performance during the commissioning phase will be given.

  8. Spray drying of budesonide, formoterol fumarate and their composites-II. Statistical factorial design and in vitro deposition properties.

    Science.gov (United States)

    Tajber, L; Corrigan, O I; Healy, A M

    2009-02-09

    The aim of this study was to investigate the effect of changing spray drying parameters on the production of a budesonide/formoterol fumarate 100:6 (w/w) composite. The systems were spray dried as solutions from 95% ethanol/5% water (v/v) using a Büchi 191-Mini Spray Dryer. A 2(5-1) factorial design study was undertaken to assess the consequence of altering spray drying processing variables on particle characteristics. The processing parameters that were studied were inlet temperature, spray drier airflow rate, pump rate, aspirator setting and feed concentration. Each batch of the resulting powder was characterised in terms of thermal and micromeritic properties as well as an in vitro deposition by twin impinger analysis. Overall, the parameter that had the greatest influence on each response investigated was production yield - airflow (higher airflow giving greater yields), median particle size - airflow (higher airflow giving smaller particle sizes) and Carr's compressibility index - feed concentration (lower feed concentration giving smaller Carr's indices). A six- to seven-fold difference in respirable fraction can be observed by changing the spray drying process parameters. The co-spray dried composite system which displayed best in vitro deposition characteristics, showed a 2.6-fold increase in respirable fraction in the twin impinger experiments and better dose uniformity compared with the physical mix of micronised powders.

  9. Conceptual design and neutronics analyses of a fusion reactor blanket simulation facility

    International Nuclear Information System (INIS)

    Beller, D.E.

    1986-01-01

    A new conceptual design of a fusion reactor blanket simulation facility was developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBR), because experiments conducted in it have resulted in the discovery of deficiencies in neutronics prediction methods. With this design, discrepancies between calculation and experimental data can be fully attributed to calculation methods because design deficiencies that could affect results are insignificant. Inelastic scattering cross sections are identified as a major source of these discrepancies. The conceptual design of this FBBR analog, the fusion reactor blanket facility (FRBF), is presented. Essential features are a cylindrical geometry and a distributed, cosine-shaped line source of 14-MeV neutrons. This source can be created by sweeping a deuteron beam over an elongated titanium-tritide target. To demonstrate that the design of the FRBF will not contribute significant deviations in experimental results, neutronics analyses were performed: results of comparisons of 2-dimensional to 1-dimensional predictions are reported for two blanket compositions. Expected deviations from 1-D predictions which are due to source anisotropy and blanket asymmetry are minimal. Thus, design of the FRBF allows simple and straightforward interpretation of the experimental results, without a need for coarse 3-D calculations

  10. Conceptual design of a fission-based integrated test facility for fusion reactor components

    International Nuclear Information System (INIS)

    Watts, K.D.; Deis, G.A.; Hsu, P.Y.S.; Longhurst, G.R.; Masson, L.S.; Miller, L.G.

    1982-01-01

    The testing of fusion materials and components in fission reactors will become increasingly important because of lack of fusion engineering test devices in the immediate future and the increasing long-term demand for fusion testing when a fusion reactor test station becomes available. This paper presents the conceptual design of a fission-based Integrated Test Facility (ITF) developed by EG and G Idaho. This facility can accommodate entire first wall/blanket (FW/B) test modules such as those proposed for INTOR and can also accommodate smaller cylindrical modules similar to those designed by Oak Ridge National laboratory (ORNL) and Westinghouse. In addition, the facility can be used to test bulk breeder blanket materials, materials for tritium permeation, and components for performance in a nuclear environment. The ITF provides a cyclic neutron/gamma flux as well as the numerous module and experiment support functions required for truly integrated tests

  11. Optimization of a pharmaceutical freeze-dried product and its process using an experimental design approach and innovative process analyzers.

    Science.gov (United States)

    De Beer, T R M; Wiggenhorn, M; Hawe, A; Kasper, J C; Almeida, A; Quinten, T; Friess, W; Winter, G; Vervaet, C; Remon, J P

    2011-02-15

    The aim of the present study was to examine the possibilities/advantages of using recently introduced in-line spectroscopic process analyzers (Raman, NIR and plasma emission spectroscopy), within well-designed experiments, for the optimization of a pharmaceutical formulation and its freeze-drying process. The formulation under investigation was a mannitol (crystalline bulking agent)-sucrose (lyo- and cryoprotector) excipient system. The effects of two formulation variables (mannitol/sucrose ratio and amount of NaCl) and three process variables (freezing rate, annealing temperature and secondary drying temperature) upon several critical process and product responses (onset and duration of ice crystallization, onset and duration of mannitol crystallization, duration of primary drying, residual moisture content and amount of mannitol hemi-hydrate in end product) were examined using a design of experiments (DOE) methodology. A 2-level fractional factorial design (2(5-1)=16 experiments+3 center points=19 experiments) was employed. All experiments were monitored in-line using Raman, NIR and plasma emission spectroscopy, which supply continuous process and product information during freeze-drying. Off-line X-ray powder diffraction analysis and Karl-Fisher titration were performed to determine the morphology and residual moisture content of the end product, respectively. In first instance, the results showed that - besides the previous described findings in De Beer et al., Anal. Chem. 81 (2009) 7639-7649 - Raman and NIR spectroscopy are able to monitor the product behavior throughout the complete annealing step during freeze-drying. The DOE approach allowed predicting the optimum combination of process and formulation parameters leading to the desired responses. Applying a mannitol/sucrose ratio of 4, without adding NaCl and processing the formulation without an annealing step, using a freezing rate of 0.9°C/min and a secondary drying temperature of 40°C resulted in

  12. Development of technical design for waste processing and storage facilities for Novi Han repository

    International Nuclear Information System (INIS)

    Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

    2005-01-01

    Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

  13. 40 CFR Table 1 to Subpart Cb of... - Nitrogen Oxides Guidelines for Designated Facilities

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Nitrogen Oxides Guidelines for... September 20, 1994 Pt. 60, Subpt. Cb, Table 1 Table 1 to Subpart Cb of part 60—Nitrogen Oxides Guidelines for Designated Facilities Municipal waste combustor technology Before April 28, 2009,nitrogen oxides...

  14. 78 FR 40015 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2013-07-03

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; District of Columbia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units AGENCY: Environmental... negative declaration for hospital/medical/infectious waste incinerator (HMIWI) units within the District of...

  15. 75 FR 78952 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-12-17

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; Commonwealth of Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative... Quality, 629 East Main Street, Richmond, Virginia 23219. FOR FURTHER INFORMATION CONTACT: James B. Topsale...

  16. 75 FR 78916 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-12-17

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, Commonwealth of Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative... 19103. Copies of the State submittal are available at the Virginia Department of Environmental Quality...

  17. 77 FR 3389 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2012-01-24

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, State of West Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units, Plan Revision... final action to approve a revision to the West Virginia hospital/medical/infectious waste incinerator...

  18. 78 FR 40087 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2013-07-03

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; District of Columbia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units AGENCY: Environmental...) section 111(d)/129 negative declaration for the District of Columbia for hospital/medical/infectious waste...

  19. 75 FR 73967 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-11-30

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, State of Delaware; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative Declaration... Environmental Control, 89 Kings Highway, P.O. Box 1401, Dover, Delaware 19903. FOR FURTHER INFORMATION CONTACT...

  20. 75 FR 73996 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-11-30

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; State of Delaware; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative Declaration... Resources and Environmental Control, 89 Kings Highway, P.O. Box 1401, Dover, Delaware 19903. FOR FURTHER...