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Book Conceptual Design of a Nuclear Waste Vitrification Facility

Download or read book Conceptual Design of a Nuclear Waste Vitrification Facility written by Pacific Northwest Laboratory and published by . This book was released on 1978 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Conceptual Design of a Nuclear Waste Vitrification Facility

Download or read book Conceptual Design of a Nuclear Waste Vitrification Facility written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document describes a conceptual high-level waste immobilization facility. The facility would have the capability to calcine and then vitrify high-level liquid waste (HLLW). The vitrification would be accomplished in a canister which is seal-welded, checked for integrity, and decontaminated for movement to storage. Included in the facility would be the capability to repair faulty canister-lid seal welds, overpack failed canisters, and treat the process off-gas and cell ventilation air prior to release to the fuel reprocessing plant (FRP) atmospheric protection system (APS). The nuclear waste vitrification facility (NWVF) would be an integral part of the FRP structure. The operations of the facilities would be centered in the waste vitrification cell (WVC) which performs most of the facility functions. The cell is a reinforced concrete hot cell, lined with stainless steel. Most operation and maintenance activities would be performed remotely using a crane equipped with an impact wrench or yoke. The major facility equipment includes a feed tank, spray calciner, two melters, weld-inspection stations, canister storage rack, and a canister decontamination cubicle. Installation and removal of equipment in the cell would be done through shielding doors. The air lock system of the canister decontamination cubicle would permit placement and removal of the canister. Activities in the cell may be observed through four shielding glass windows and/or up to three periscopes. The operating, service, and pipe galleries which house operating personnel and equipment necessary for cell operations are located adjacent to the cell.

Book Letter Report  Pre conceptual Design Study for a Pilot scale Non Radioactive Low Level Waste Vitrification Facility

Download or read book Letter Report Pre conceptual Design Study for a Pilot scale Non Radioactive Low Level Waste Vitrification Facility written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents a pre-conceptual design study for a Non-Radioactive Low-Level Waste, Pilot-Scale Vitrification System. This pilot plant would support the development of a full-scale LLW Vitrification Facility and would ensure that the full-scale facility can meet its programmatic objectives. Use of the pilot facility will allow verification of process flowsheets, provide data for ensuring product quality, assist in scaling to full scale, and support full-scale start-up. The facility will vitrify simulated non-radioactive LLW in a manner functionally prototypic to the full-scale facility. This pre-conceptual design study does not fully define the LLW Pilot-Scale Vitrification System; rather, it estimates the funding required to build such a facility. This study includes identifying all equipment necessary. to prepare feed, deliver it into the melter, convert the feed to glass, prepare emissions for atmospheric release, and discharge and handle the glass. The conceived pilot facility includes support services and a structure to contain process equipment.

Book A disposal centre for immobilized nuclear waste   conceptual design study

Download or read book A disposal centre for immobilized nuclear waste conceptual design study written by and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Conceptual Design Report for Remote Handled Low Level Waste Disposal Facility

Download or read book Conceptual Design Report for Remote Handled Low Level Waste Disposal Facility written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Site Characterization Plan Conceptual Design Report for a High level Nuclear Waste Repository in Salt  Vertical Emplacement Mode

Download or read book Site Characterization Plan Conceptual Design Report for a High level Nuclear Waste Repository in Salt Vertical Emplacement Mode written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.

Book Conceptual Design Report for the Remote Handled Low Level Waste Disposal Project

Download or read book Conceptual Design Report for the Remote Handled Low Level Waste Disposal Project written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Conceptual Design Report for Central Waste Disposal Facility

Download or read book Conceptual Design Report for Central Waste Disposal Facility written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Radioactive Waste Processing and Disposal

Download or read book Radioactive Waste Processing and Disposal written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 908 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Design and Operation of High Level Waste Vitrification and Storage Facilities

Download or read book Design and Operation of High Level Waste Vitrification and Storage Facilities written by International Atomic Energy Agency and published by . This book was released on 1992 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report gives an up to date review of high level waste vitrification and storage facilities currently in an advanced stage of implementation.

Book Conceptual Design Report for the ICPP Spent Nuclear Fuel Dry Storage Project

Download or read book Conceptual Design Report for the ICPP Spent Nuclear Fuel Dry Storage Project written by and published by . This book was released on 1996 with total page 432 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Surface Feature Characterization Test Plan

Download or read book Surface Feature Characterization Test Plan written by and published by . This book was released on 1984 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Site Characterization Plan

Download or read book Site Characterization Plan written by and published by . This book was released on 1987 with total page 817 pages. Available in PDF, EPUB and Kindle. Book excerpt: The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Low level Waste Vitrification Pilot scale System Need Report

Download or read book Low level Waste Vitrification Pilot scale System Need Report written by and published by . This book was released on 1996 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report examines the need for pilot-scale testing in support of the low-level vitrification facility at Hanford. In addition, the report examines the availability of on-site facilities to contain a pilot-plant. It is recommended that a non-radioactive pilot-plant be operated for extended periods. In addition, it is recommended that two small-scale systems, one processing radioactive waste feed and one processing a simulated waste feed be used for validation of waste simulants. The actual scale of the pilot-plant will be determined from the technologies included in conceptual design of the plant. However, for the purposes of this review, a plant of 5 to 10 metric ton/day of glass production was assumed. It is recommended that a detailed data needs package and integrated flowsheet be developed in FY95 to clearly identify data requirements and identify relationships with other TWRS elements. A pilot-plant will contribute to the reduction of uncertainty in the design and initial operation of the vitrification facility to an acceptable level. Prior to pilot-scale testing, the components will not have been operated as an integrated system and will not have been tested for extended operating periods. Testing for extended periods at pilot-scale will allow verification of the flowsheet including the effects of recycle streams. In addition, extended testing will allow evaluation of wear, corrosion and mechanical reality of individual components, potential accumulations within the components, and the sensitivity of the process to operating conditions. Also, the pilot facility will provide evidence that the facility will meet radioactive and nonradioactive environmental release limits, and increase the confidence in scale-up. The pilot-scale testing data and resulting improvements in the vitrification facility design will reduce the time required for cold chemical testing in the vitrification facility.