Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 6].

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ISBN 13 :
Total Pages : 721 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 6]. by :

Download or read book Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 6]. written by and published by . This book was released on 2002 with total page 721 pages. Available in PDF, EPUB and Kindle. Book excerpt: In February 1995, the US. Department of Energy (DOE) approved the Spent Nuclear Fuel (SNF) Project's ''Path Forward'' recommendation for resolution of the safety and environmental concerns associated with the deteriorating SNF stored in the Hanford Site's K Basins (Hansen 1995). The recommendation included an aggressive series of projects to design, construct, and operate systems and facilities to permit the safe retrieval, packaging, transport, conditioning, and interim storage of the K Basins' SNF. The facilities are the Cold Vacuum Drying Facility (CVDF) in the 100 K Area of the Hanford Site and the Canister Storage Building (CSB) in the 200 East Area. The K Basins' SNF is to be cleaned, repackaged in multi-canister overpacks (MCOs), removed from the K Basins, and transported to the CVDF for drying. The MCOs would then be moved to the CSB and weld sealed (Loscoe 1996) for interim storage (about 40 years). One of the major tasks associated with the initial Path Forward activities is the development and maintenance of the safety documentation. In addition to meeting the construction needs for new structures, the safety documentation for each must be generated. A common thread that was identified among the structures was the MCO. Each structure exists for the specific purpose of treating or storing the MCO and its contents. Normally, an extensive amount of MCO-related documentation would be generated for each of the facility safety analysis reports. However, the expedited schedule for removing spent fuel from the K Basins requires that the documentation effort be minimized and repetitious activities be eliminated. Therefore, this topical report has been prepared to address those aspects of the MCO that will be common to the facilities. The MCO will be included in each facility's safety documentation by reference to this topical report. By capturing the design of the MCO and its safety evaluation in a single document, repetition, inconsistency, and duplication of effort is minimized. As changes are made to the MCO, the MCO Topical Report can be updated to retain the validity of references to the report. By submitting the topical report for early review and approval, it will be possible for the facility safety analysis reports to reference the Topical Report for much of the MCO design information.

Multi Canister Overpack (MCO) Topical Report [SEC 1 and 2].

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ISBN 13 :
Total Pages : 670 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Multi Canister Overpack (MCO) Topical Report [SEC 1 and 2]. by :

Download or read book Multi Canister Overpack (MCO) Topical Report [SEC 1 and 2]. written by and published by . This book was released on 1999 with total page 670 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 3].

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ISBN 13 :
Total Pages : 699 pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 3]. by :

Download or read book Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 3]. written by and published by . This book was released on 2000 with total page 699 pages. Available in PDF, EPUB and Kindle. Book excerpt: In February 1995, the US Department of Energy (DOE) approved the Spent Nuclear Fuel (SNF) Project's ''Path Forward'' recommendation for resolution of the safety and environmental concerns associated with the deteriorating SNF stored in the Hanford Site's K Basins (Hansen 1995). The recommendation included an aggressive series of projects to design, construct, and operate systems and facilitates to permit the safe retrieval, packaging, transport, conditions, and interim storage of the K Basins' SNF. The facilities are the Cold VAcuum Drying Facility (CVDF) in the 100 K Area of the Hanford Site and the Canister Storage building (CSB) in the 200 East Area. The K Basins' SNF is to be cleaned, repackaged in multi-canister overpacks (MCOs), removed from the K Basins, and transported to the CVDF for initial drying. The MCOs would then be moved to the CSB and weld sealed (Loscoe 1996) for interim storage (about 40 years). One of the major tasks associated with the initial Path Forward activities is the development and maintenance of the safety documentation. In addition to meeting the construction needs for new structures, the safety documentation for each must be generated.

Multi-canister Overpack Design Report

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ISBN 13 :
Total Pages : 792 pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis Multi-canister Overpack Design Report by :

Download or read book Multi-canister Overpack Design Report written by and published by . This book was released on 1999 with total page 792 pages. Available in PDF, EPUB and Kindle. Book excerpt: Revision 2 incorporates changes to reflect a 150 psig pressure rating for the mechanically closed MCO and 450 psig pressure rating with the cover cap welded in place, per the MCO Performance Specification, HNF-S-0426, Rev. 5.

Analysis for Eccentric Multi Canister Overpack (MCO) Drops at the Canister Storage Building (CSB) (CSB-S-0073).

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Analysis for Eccentric Multi Canister Overpack (MCO) Drops at the Canister Storage Building (CSB) (CSB-S-0073). by :

Download or read book Analysis for Eccentric Multi Canister Overpack (MCO) Drops at the Canister Storage Building (CSB) (CSB-S-0073). written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this report is to investigate the potential for damage to the multi-canister overpack (MCO) during impact from an eccentric accidental drop onto the standard storage tube, overpack storage tube, service station or sampling/weld station. Damage to the storage tube and sample/weld station is beyond the scope of this report. The results of this analysis are required to show the following: (1) If a breach resulting in unacceptable release of contamination could occur in the MCO. (2) If the dropped MCO could become stuck in the storage tube after the drop. (3) Maximum deceleration of the spent nuclear fuel baskets. The model appropriate for the standard storage tubes with the smaller gap is the basis for the analysis and results reported herein in this SNF-5204, revision 2 report. Revision 1 of this report is based on a model that includes the larger gap appropriate for the overpack tubes.

Multicanister Overpack Topical Report

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ISBN 13 :
Total Pages : 920 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Multicanister Overpack Topical Report by :

Download or read book Multicanister Overpack Topical Report written by and published by . This book was released on 1997 with total page 920 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Spent Nuclear Fuel MCO is a single-use container that consists of a cylindrical shell, five to six fuel baskets, a shield plug, and features necessary for maintaining the structural integrity of the MCO while providing criticality control and fuel processing capability.

Multi-canister Overpack Design Report

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ISBN 13 :
Total Pages : 997 pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis Multi-canister Overpack Design Report by :

Download or read book Multi-canister Overpack Design Report written by and published by . This book was released on 1997 with total page 997 pages. Available in PDF, EPUB and Kindle. Book excerpt: This design report documents the final design for the Multi-Canister Overpack.

Safety Analysis Report for Packaging (Onsite) Multi Canister Overpack Cask

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ISBN 13 :
Total Pages : 1013 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Safety Analysis Report for Packaging (Onsite) Multi Canister Overpack Cask by :

Download or read book Safety Analysis Report for Packaging (Onsite) Multi Canister Overpack Cask written by and published by . This book was released on 2001 with total page 1013 pages. Available in PDF, EPUB and Kindle. Book excerpt: This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the Multi-canister Overpack (MCO) and MCO Cask and Shippingport Spent Fuel Canister for a highway route controlled quantity, Type B, fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.

DESIGN OF THE HANFORD MULTI CANISTER OVERPACK (MCO) & DEVELOPMENT & QUALIFICATION OF THE CLOSURE WELDING PROCESS.

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ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis DESIGN OF THE HANFORD MULTI CANISTER OVERPACK (MCO) & DEVELOPMENT & QUALIFICATION OF THE CLOSURE WELDING PROCESS. by :

Download or read book DESIGN OF THE HANFORD MULTI CANISTER OVERPACK (MCO) & DEVELOPMENT & QUALIFICATION OF THE CLOSURE WELDING PROCESS. written by and published by . This book was released on 2004 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Processing more than 2,100 metric tons of metallic uranium spent nuclear fuel (SNF) into large stainless steel containers called Multi-Canister Overpacks (MCOs) is one of the top priorities for the Department of Energy (DOE) at the Hanford Site, located in southeastern Washington state. The MCOs will be temporarily stored on site and eventually shipped to the federal geologic repository for long-term storage. MCOs are constructed and ''N''stamped in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Section III, Division 1, Class 1 Components. Final closure welding poses a challenge after the fuel is loaded. Performing required examination and testing activities (volumetric examination and hydrostatic leak testing) can be difficult, if not impractical. An ASME Code Case N-595-3, was written specifically to allow code stamping by addressing such closures and providing alternative rules. MCOs are the first SNF canisters within the DOE complex to successfully use this code case for receiving ASME stamps. This paper discusses the design of the MCO, application of the N-595-3 code case, and development and qualification of the final welded closure. The MCO design considers internal pressure and handling loads, as well as processing and interim storage activities. The MCO functions as the primary or innermost containment as part of an overall transportation package so the design also considered interface features with secondary and transport containers. The MCO, approximately 2 feet in diameter and nearly 14 feet tall, is constructed primarily of Type 304/304L stainless steel and the final pressure boundary is of all-welded construction. The closure-weld is made with the Gas Tungsten Arc Welding (GTAW) process, using an automatic, machine-welding mode. Examination and testing of the closure includes the N-595-3 specified requirements-progressive Liquid Penetrant testing (PT) and final helium leak testing. At completion of the closure, the MCO is ''N'' stamped as a 450 pounds per square inch (design pressure) vessel. To ensure the process consistently achieves the required weld penetration, a series of developmental tests was performed to identify an optimum and robust set of welding parameters. Testing included test welds made on plate mockups and then actual MCO mockups. With the primary welding parameters (welding current and travel speed) established, a simple two-factor, two-level, factorial experiment with replication at high and low heat input conditions was conducted. Evaluation of the results included weld photomicrographs, which helped establish process range limits for these parameters broad enough to cover typical equipment and measurement variations and provide additional operating margin. To date, over 316 MCOs have been loaded, dried, and transported to the Canister Storage Building (CSB), where the welding is done. Of those, 161 MCOs have received final welded closure and ''N'' stamps. All cover cap final closure welds have met specified requirements without incident.

Warehouse Plan for the Multi Canister Overpacks (MCO) and Baskets

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ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Warehouse Plan for the Multi Canister Overpacks (MCO) and Baskets by :

Download or read book Warehouse Plan for the Multi Canister Overpacks (MCO) and Baskets written by and published by . This book was released on 2000 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Multi-Canister Overpacks (MCOs) will contain spent nuclear fuel (SNF) removed from the K East and West Basins. The SNF will be placed in fuel storage baskets that will be stacked inside the MCOs. Approximately 400 MCOS and 2170 baskets will fabricated for this purpose. These MCOs, loaded with SNF, will be placed in interim storage in the Canister Storage Building (CSB) located in the 200 Area of the Hanford Site.

ASME Code Requirements for Multi-canister Overpack Design and Fabrication

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ISBN 13 :
Total Pages : 20 pages
Book Rating : 4.:/5 (683 download)

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Book Synopsis ASME Code Requirements for Multi-canister Overpack Design and Fabrication by :

Download or read book ASME Code Requirements for Multi-canister Overpack Design and Fabrication written by and published by . This book was released on 1998 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: The baseline requirements for the design and fabrication of the MCO include the application of the technical requirements of the ASME Code, Section III, Subsection NB for containment and Section III, Subsection NG for criticality control. ASME Code administrative requirements, which have not historically been applied at the Hanford site and which have not been required by the US Nuclear Regulatory Commission (NRC) for licensed spent fuel casks/canisters, were not invoked for the MCO. As a result of recommendations made from an ASME Code consultant in response to DNFSB staff concerns regarding ASME Code application, the SNF Project will be making the following modifications: issue an ASME Code Design Specification and Design Report, certified by a Registered Professional Engineer; Require the MCO fabricator to hold ASME Section III or Section VIII, Division 2 accreditation; and Use ASME Authorized Inspectors for MCO fabrication. Incorporation of these modifications will ensure that the MCO is designed and fabricated in accordance with the ASME Code. Code Stamping has not been a requirement at the Hanford site, nor for NRC licensed spent fuel casks/canisters, but will be considered if determined to be economically justified.

1900 Census, Upper Montgomery County, Maryland

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ISBN 13 :
Total Pages : 198 pages
Book Rating : 4.:/5 (396 download)

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Book Synopsis 1900 Census, Upper Montgomery County, Maryland by :

Download or read book 1900 Census, Upper Montgomery County, Maryland written by and published by . This book was released on 199? with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Drop Testing Representative Multi-Canister Overpacks

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ISBN 13 :
Total Pages : 192 pages
Book Rating : 4.:/5 (925 download)

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Book Synopsis Drop Testing Representative Multi-Canister Overpacks by :

Download or read book Drop Testing Representative Multi-Canister Overpacks written by and published by . This book was released on 2015 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of the work reported herein was to determine the ability of the Multi- Canister Overpack (MCO) canister design to maintain its containment boundary after an accidental drop event. Two test MCO canisters were assembled at Hanford, prepared for testing at the Idaho National Engineering and Environmental Laboratory (INEEL), drop tested at Sandia National Laboratories, and evaluated back at the INEEL. In addition to the actual testing efforts, finite element plastic analysis techniques were used to make both pre-test and post-test predictions of the test MCOs structural deformations. The completed effort has demonstrated that the canister design is capable of maintaining a 50 psig pressure boundary after drop testing. Based on helium leak testing methods, one test MCO was determined to have a leakage rate not greater than 1x10-5 std cc/sec (prior internal helium presence prevented a more rigorous test) and the remaining test MCO had a measured leakage rate less than 1x10-7 std cc/sec (i.e., a leaktight containment) after the drop test. The effort has also demonstrated the capability of finite element methods using plastic analysis techniques to accurately predict the structural deformations of canisters subjected to an accidental drop event.

Warehouse Plan for the Multi Canister Overpack (MC0) and Baskets

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ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Warehouse Plan for the Multi Canister Overpack (MC0) and Baskets by :

Download or read book Warehouse Plan for the Multi Canister Overpack (MC0) and Baskets written by and published by . This book was released on 2000 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Multi-Canister Overpacks (MCO) will contain spent nuclear fuel (SNF) removed from the K East and West Basins. The SNF will be placed in fuel storage baskets that will be stacked inside the MCOs. Approximately 400 MCOs and 21 70 baskets will be fabricated for this purpose. These MCOs, loaded with SNF, will be placed in interim storage in the Canister Storage Building (CSB) located in the 200 Area of the Hanford Site. The MCOs consist of different components/sub-assemblies that will be manufactured by one or more vendors. All component/sub-assemblies will be shipped to the Hanford Site Central Stores Warehouse, 2355 Stevens Drive, Building 1163 in the 1100 Area, for inspection and storage until these components are required at the CSB and K Basins. The MCO fuel storage baskets will be manufactured in the MCO basket fabrication shop located in Building 328 of the Hanford Site 300 Area. The MCO baskets will be inspected at the fabrication shop before shipment to the Central Stores Warehouse for storage. The MCO components and baskets will be stored as received from the manufacturer with specified protective coatings, wrappings, and packaging intact to maintain mechanical integrity of the components and to prevent corrosion. The components and baskets will be shipped as needed from the warehouse to the CSB and K Basins. This warehouse plan includes the requirements for receipt of MCO components and baskets from the manufacturers and storage at the Hanford Site Central Stores Warehouse. Transportation of the MCO components and baskets from the warehouse, unwrapping, and assembly of the MCOs are the responsibility of SNF Operations and are not included in this plan.

Catalogue d'un mobilier... Vente 9 déc. 1853...

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (465 download)

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Book Synopsis Catalogue d'un mobilier... Vente 9 déc. 1853... by :

Download or read book Catalogue d'un mobilier... Vente 9 déc. 1853... written by and published by . This book was released on 1853 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Multi-Canister Overpack Design Pressure Rating

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ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.:/5 (683 download)

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Book Synopsis Multi-Canister Overpack Design Pressure Rating by :

Download or read book Multi-Canister Overpack Design Pressure Rating written by and published by . This book was released on 1998 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: The SNF project was directed to increase the MCO pressure rating by the U.S. Department of Energy, Richland Operations Office (RL) unless the action was shown to be cost prohibitive. This guidance was driven by RL's assessment that there was a need to improve margin and reduce risks associated with assumptions supporting the bounding pressure calculation for the MCO Sealing Strategy. Although more recent pressure analyses show a bounding MCO pressure of 50 psig, RL still considers it prudent to retain the pressure margin the 450 psig rating provides. This rating creates a real, clearly definable margin and significantly reduces the risk that the safety basis will be challenged.

Multi-Canister Overpack Tropical Report

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ISBN 13 :
Total Pages : 49 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Multi-Canister Overpack Tropical Report by :

Download or read book Multi-Canister Overpack Tropical Report written by and published by . This book was released on 2002 with total page 49 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document identifies all ''safety equipment'', and certain other ''safety-related'' equipment, for core sampling of currently stored radioactive waste in Hanford single-shell tanks. It includes both Push Mode Core Sampling (PMCS) and Rotary Mode Core Sampling (RMCS) systems. This revision, Rev. 3, is an annual update reflecting changes in the Authorization Basis. The safety classification designation is used as the basis for confirming the appropriate Quality, Safety, and Environmental Assurance, and Quality Control used for design work, procurement, installation/modification, maintenance, and operation of equipment.