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Book Multi Canister Overpack Number of Shield Plug Ports

Download or read book Multi Canister Overpack Number of Shield Plug Ports written by and published by . This book was released on 1998 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Multi Canister Overpack MCO Design Report SEC 1 Thru 3

Download or read book Multi Canister Overpack MCO Design Report SEC 1 Thru 3 written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The MCO is designed to facilitate the removal, processing and storage of the spent nuclear fuel currently stored in the East and West K-Basins. The MCO is a stainless steel canister approximately 24 inches in diameter and 166 inches long with cover cap installed. The shell and the collar which is welded to the shell are fabricated from 304/304L dual certified stainless steel for the shell and F304/F304L dual certified for the collar. The shell has a nominal thickness of 1/2 inch. The top closure consists of a shield plug with four processing ports and a locking ring with jacking bolts to pre-load a metal seal under the shield plug. The fuel is placed in one of four types of baskets, excluding the SPR fuel baskets, in the fuel retention basin. Each basket is then loaded into the MCO which is inside the transfer cask. Once all of the baskets are loaded into the MCO, the shield plug with a process tube is placed into the open end of the MCO. This shield plug provides shielding for workers when the transfer cask, containing the MCO, is lifted from the pool. After being removed from the pool, the locking ring is installed and the jacking bolts are tightened to pre-load the metal main closure seal. The cask is then sealed and the MCO taken to the Cold Vacuum Drying (CVD) facility for bulk water removal and vacuum drying through the process ports. Covers for the process ports may be installed or removed as needed per operating procedures. The MCO is then transferred to the Canister Storage Building (CSB), in the closed transfer cask. At the CSB, the MCO is then removed from the cask and becomes one of two MCOs stacked in a storage tube. MCOs will have a cover cap welded over the shield plug providing a complete welded closure. A number of MCOs may be stored with just the mechanical seal to allow monitoring of the MCO pressure, temperature, and gas composition.

Book Multi Canister Overpack MCO Closure Welding Process Parameter Development and Qualification

Download or read book Multi Canister Overpack MCO Closure Welding Process Parameter Development and Qualification written by and published by . This book was released on 2003 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the Department of Energy's (DOE) top priorities at the Hanford Site (southeastern Washington state), is the processing of more than 2,000 tons of spent nuclear fuel (SNF) into large stainless steel containers called Multi-Canister Overpacks (MCO). Packaging into MCO's will assist in the safe and economic disposition of SNF and greatly reduce risk to the environment. Packaged fuel will be removed from close proximity to the Columbia River to a more suitable area of the site where it will be stored on an interim basis. Eventually, the fuel will be transferred to the federal geologic repository for long-term storage. One of the key elements in the SNF process is final closure of the MCO by welding. Fuel is loaded into the MCO (approximately 2 ft. in diameter and 13 ft. long) and a heavy shield plug inserted into the top, creating a mechanical seal. The plug contains several process ports for various operations, including vacuum drying and inert-gas backfilling of the packaged fuel. When fully processed, the Canister Cover Assembly (CCA) is placed over the shield plug and final closure made by welding. The following describes the effort to develop and qualify the root-pass technique associated with the MCO final closure weld.

Book Nuclear Engineering International

Download or read book Nuclear Engineering International written by and published by . This book was released on 1995 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Evaluation of Tin Plating for Multi Canister Overpack Seals

Download or read book Evaluation of Tin Plating for Multi Canister Overpack Seals written by and published by . This book was released on 2000 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Multi-Canister Overpack (MCO) incorporates plated seals for use with (1) the port cover plates, (2) process valves of the shield plug, and (3) test plug ofthe cover cap. These seals are required to maintain leakage rates as low as 10−7 scc/atm-sec. in the cover cap to test plug seal. The seals are manufactured by EG & G division of Perkin Elmer. Currently, the MCO design calls for use of silver or gold plated seals in these locations. The seal plating materials are deposited on Inconel 718 or X-750 substrates. Some of these seals are reused several times in service on the MCO. The MCO manufacturer has built several MCOs and is in the leak testing stage and has had great difficulty obtaining acceptable leakage rates at their plant in Camden, New Jersey. The seal manufacturer was called in to evaluate the situation and now the seal manufacturer recommends tin plated seals. This evaluation examines the Corrosion resistance and thermal stability of tin plating on the seals. The use of tin plating on MCO seals was evaluated for corrosion resistance and thermal stability. The corrosion resistance of tin in the expected MCO environments is acceptable. The effect of radiation hardening will offset creep deformation results. However, a low melting point indicates unsuitability at significantly elevated temperatures.

Book Warehouse Plan for the Multi Canister Overpack MC0 and Baskets

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.

Book Warehouse Plan for the Multi Canister Overpacks MCO and Baskets

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.

Book Waste Management and Fuel Cycles

Download or read book Waste Management and Fuel Cycles written by and published by . This book was released on 1978 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Technical Progress Report for the Quarter

Download or read book Technical Progress Report for the Quarter written by and published by . This book was released on 1982 with total page 210 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Transportation of Used Fuel

Download or read book Transportation of Used Fuel written by and published by . This book was released on 1992 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Liquid Metal Fast Breeder Reactor Program sec 4 Environmental impact of the LMFBR fuel cycle sec 5 Economic social and other impacts

Download or read book Liquid Metal Fast Breeder Reactor Program sec 4 Environmental impact of the LMFBR fuel cycle sec 5 Economic social and other impacts written by and published by . This book was released on 1974 with total page 982 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Liquid Metal Fast Breeder Reactor Program

Download or read book Liquid Metal Fast Breeder Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1974 with total page 1004 pages. Available in PDF, EPUB and Kindle. Book excerpt: