scholarly journals US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 4, Site specific---Ohio through South Carolina

1993 ◽  
Author(s):  
◽  
◽  
◽  
Keyword(s):  
South Carolina ◽  
Department Of Energy ◽  
Waste Streams ◽  
Site Specific ◽  
Mixed Waste

Formation of Nanofibers from Pure and Mixed Waste Streams Using Electrospinning

2015 ◽  
Vol 54 (37) ◽  
pp. 9057-9063 ◽  
Author(s):  
Nicole E. Zander ◽  
Daniel Sweetser ◽  
Daniel P. Cole ◽  
Margaret Gillan
Keyword(s):  
Waste Streams ◽  
Mixed Waste

Design and Analysis of a Camera and Sensor Positioning Mechanism for ARIES: An Autonomous Mobile Robot

1998 ◽  
Author(s):  
David N. Rocheleau ◽  
Matthew M. Moore
Keyword(s):  
South Carolina ◽  
Mobile Robot ◽  
Mechanical Design ◽  
Experimental System ◽  
Department Of Energy ◽  
Autonomous Mobile Robot ◽  
University Of South Carolina ◽  
Clemson University ◽  
Lift Mechanism ◽  
Sensor Package

Abstract ARIES (Autonomous Robotic Inspection Experimental System) is a program for the Department of Energy (DOE) that was charged with the mission of surveying and inspecting drums containing low-level radioactive waste stored in warehouses at DOE facilities. This paper reports on the final development of the ARIES project, and focuses on the mechanical design and analysis of three mechanisms that position a camera and sensor package that sits atop a Cybermotion K3A mobile robotic platform. The ARIES project was executed through a joint effort of three parties: University of South Carolina (USC), Clemson University, and Cybermotion, Inc., of Salem, Virginia. The goal of the project was to develop an autonomous mobile robot that positions a data acquisition package (DAP) which surveys drums containing hazardous materials in Department of Energy (DOE) warehouses. The unique mechanical design of the positioning system is comprised of three distinct components: a lift mechanism, a fourbar mechanism, and a camera panning mechanism. The components are integrated in a manner that allows the DAP to be positioned from 0 to 16 feet off the ground while the robot maneuvers through aisles of drums in a warehouse. The three mechanisms, and the integration thereof, are reported in this paper.

Pressure Protection Evaluation Program at Savannah River Site

2003 ◽  
Author(s):  
James K. Chan ◽  
John W. Ramsey
Keyword(s):  
South Carolina ◽  
Computer Program ◽  
Material Handling ◽  
Nuclear Material ◽  
Savannah River Site ◽  
Pressure Vessels ◽  
Department Of Energy ◽  
Savannah River ◽  
Design Requirements ◽  
River Site

This paper describes the current pressure protection program at Savannah River Site (SRS), a Department of Energy chemical processing and nuclear material handling facility in Aiken, South Carolina. It gives a brief description of the design requirements based on ASME, API, CGA, and ASHRAE Codes. Equipment and systems requiring pressure protection at SRS are primarily pressure vessels, steam stations, process chemical systems, refrigerant and cryogenic systems and other air or gas systems. It is understood that any pressure protection program is built on five fundamental areas of responsibility: procurement, verification, registration, inspection, and repair. This paper focuses on the existing process of facility pressure protection evaluation for code compliance followed by identification of failure scenarios and system design requirements, valve selection and sizing, and verification record generation. Improvements to this process are recognized and discussed. They include the development of a computer program to perform pressure protection evaluation and generate verification records. The software would process all applicable pressure protection calculations using improved methodologies. All relevant data required would be accessible within the program. Pressure safety relief device attributes and system parameters would be displayed. The computer program would enhance design consistency, improve quality and plant safety, and make the pressure protection verification process more efficient and cost effective.

Addressing Information Gaps in Household Waste Sorting Using a Mobile Application

2019 ◽  
Author(s):  
Kelvin Østergaard Pagels ◽  
Mikkel Bayard Rasmussen ◽  
Devarajan Ramanujan
Keyword(s):  
Mobile Application ◽  
Waste Stream ◽  
Household Waste ◽  
Preliminary Survey ◽  
Waste Streams ◽  
Detailed Survey ◽  
Mixed Waste ◽  
Information Gaps

Abstract The Danish government has outlined a target of recycling 50% of total household waste by the year 2022. Improving household waste sorting is an important consideration towards achieving this goal. This paper focuses on understanding existing waste sorting practices among Danish residents and exploring whether a mobile application can help address any existing information gaps. We conducted a preliminary survey (N = 180) that assessed preference for sorting strategies and the types of waste sorted. Following this a more detailed survey was conducted (N = 357) that assessed residents’ motivation to sort household waste, knowledge of local sorting requirements, information gaps that prevent effective sorting, and need for specific features in a mobile application. Results show over one-third of respondents felt they needed additional waste sorting information. Respondents had fewer inaccuracies disposing items within a single waste stream (e.g., electronics waste) compared to items with mixed waste streams (e.g., milk carton with a plastic cap). Based on these findings we propose the design of a mobile application that can potentially improve household waste sorting.

Demonstration and Licensing of a Spent Nuclear Fuel Dry Transfer System

2001 ◽  
Author(s):  
Mikal A. McKinnon ◽  
Leroy Stewart
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Safety Analysis ◽  
The United States ◽  
Lessons Learned ◽  
Department Of Energy ◽  
Transfer System ◽  
National Academy Of Sciences ◽  
Cooperative Effort ◽  
Site Specific

Abstract Research studies by the Electric Power Research Institute (EPRI) established the technical and operational requirements necessary to enable the onsite cask-to-cask dry transfer of spent nuclear fuel. Use of the dry transfer system has the potential to permit shutdown reactor sites to decommission pools and provide the capability of transferring assemblies from storage casks or small transportation casks to sealed transportable canisters. Following an evaluation by the Department of Energy (DOE) and the National Academy of Sciences, a cooperative program was established between DOE and EPRI, which led to the cost-shared design of a dry transfer system (DTS). EPRI used Transnuclear, Inc., of Hawthorne, New York, to design the DTS in accordance with the technical and quality assurance requirements of the code of Federal Regulations, Title 10, Part 72 (10CFR72). EPRI delivered the final design report to DOE in 1995 and the DTS topical safety analysis report (TSAR) in 1996. DOE submitted the TSAR to the United States Nuclear Regulatory Commission (NRC) for review under 10CFR72 and requested that the NRC staff evaluate the TSAR and issue a Safety Evaluation Report (SER) that could be used and referenced by an applicant seeking a site-specific license for the construction and operation of a DTS. DOE also initiated a cold demonstration of major subsystem prototypes in 1996. After careful assessment, the NRC agreed that the DTS concept has merit. However, because the TSAR was not site-specific and was lacking some detailed information required for a complete review, the NRC decided to issue an Assessment Report (AR) rather than a SER. This was issued in November 2000. Additional information that must be included in a future site-specific Safety Analysis Report for the DTS is identified in the AR. The DTS consists of three major sections: a Preparation Area, a Lower Access Area, and a Transfer Confinement Area. The Preparation Area is a sheet metal building where casks are prepared for loading, unloading, or shipment. The Preparation Area adjoins the Lower Access Area and is separated from the Lower Access Area by a large shielded door. The Lower Access Area and Transfer Confinement Area are contained within concrete walls approximately three feet thick. These are the areas where the casks are located and where the fuel is moved during transfer operations. A floor containing two portals separates the Lower Access Area and the Transfer Confinement Area. The casks are located below the floor, and the fuel transfer operation occurs above the floor. The cold demonstration of the DTS was successfully conducted at the Idaho National Engineering and Environmental Laboratory (INEEL) as a cooperative effort between the DOE and EPRI. The cold demonstration was limited to the fuel handling equipment, the cask lid handling equipment, and the cask interface system. The demonstration included recovery operations associated with loss of power or off-normal events. The demonstration did not include cask receiving and lid handling; cask transport and lifting; vacuum/inerting/leak test; canister welding; decontamination; heating, ventilation, and air conditioning; and radiation monitoring. The demonstration test was designed to deliberately challenge the system and determine whether any specific system operation could adversely impact or jeopardize the operation or safety of any other function or system. All known interlocks were challenged. As in all new systems, there were lessons learned during the operation of the system and a few minor modifications made to ease operations. System modifications were subsequently demonstrated. The demonstration showed that the system operated as expected and provided times for normal fuel transfer operations. The demonstration also showed that recovery could be made from off-normal events.

Field Evaluation of High Voltage Electron Beam Technology for Treating VOC-Contaminated Groundwater. Part II: Acute Toxicity Changes and By-Product Formation

1998 ◽  
Vol 3 (1) ◽  
Author(s):  
Kirankumar Topudurti ◽  
Michael Keefe ◽  
Chriso Petropoulou ◽  
Tim Schlichting ◽  
Franklin Alvarez
Keyword(s):  
South Carolina ◽  
Electron Beam ◽  
Acute Toxicity ◽  
Organic Compounds ◽  
High Voltage ◽  
High Energy ◽  
Department Of Energy ◽  
Innovative Technology ◽  
Beam System ◽  
The U.S

AbstractAs part of the Superfund Innovative Technology Evaluation program, the U.S. Environmental Protection Agency evaluated the High Voltage jEnvironmental Applications, Inc. (HVEA), electron beam (E-beam) technology at the U.S. Department of Energy Savannah River Site (SRS) in Aiken, South Carolina. This technology irradiates water with a beam of high-energy electrons, causing the formation of three primary transient reactive species: aqueous electrons, hydroxyl radicals, and hydrogen radicals. Target organic compounds are either mineralized or broken down into low molecular weight organic compounds, primarily by these species. The E-beam system used for the evaluation is housed in an 8- by 48-foot trailer and is rated for a maximum flow rate of 50 gpm. During two different periods totaling 3 weeks in September and November 1994, about 70,000 gallons of SRS M-area groundwater contaminated with volatile organic compounds (VOCs) was treated with the E-beam system. E-beam treatment increased groundwater acute toxicity for fathead minnows but not for water fleas. Although several VOCs were removed, lack of decrease in toxicity appears to be due to formation of toxic by-products, including haloacetic acids and aldehydes, during E-beam treatment of groundwater. An increase in inorganic carbon and chloride concentrations was observed, in the treated groundwater indicating that some VOCs were mineralized during E-beam treatment. Formation of CO

scholarly journals Multiple Tier Fuel Cycle Studies for Waste Transmutation

2002 ◽  
Author(s):  
R. N. Hill ◽  
T. A. Taiwo ◽  
J. A. Stillman ◽  
D. J. Graziano ◽  
D. R. Bennett ◽  
...  
Keyword(s):  
Mass Flow ◽  
System Performance ◽  
Fuel Cycle ◽  
Department Of Energy ◽  
Waste Streams ◽  
Fuel Processing ◽  
Advanced Fuel ◽  
Support Ratio ◽  
Plutonium Separation ◽  
The U.S

As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (∼0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system.

Does Erosion Corrosion Account for Intriguing Damage to the Civil War Submarine H.L. Hunley?1

2012 ◽  
Vol 46 (6) ◽  
pp. 38-48 ◽  
Author(s):  
Maria Jacobsen ◽  
Vincent Y. Blouin ◽  
William Shirley
Keyword(s):  
South Carolina ◽  
Civil War ◽  
Marine Environment ◽  
Combined Effects ◽  
Site Specific ◽  
Erosion Corrosion ◽  
Ballast Tanks

AbstractExcavation of the Civil War submarine H.L. Hunley, raised from the seabed off Charleston, South Carolina, has revealed large hull breaches in the fore and aft sections of the vessel. Initially, the damage was thought to have occurred the night the pioneering submarine sank in 1864, but recent hull forensic studies indicate that the two largest breaches in the submarine’s ballast tanks occurred due to natural and site-specific seabed conditions and did not contribute to the submarine’s demise. To reconstruct and interpret these conditions, a new methodology has been developed that utilizes forensic data embedded in the marine concretion covering the iron hull. Results from an experiment conducted to test the theory further support the notion that the largest breaches were likely caused by the combined effects of erosion and corrosion of the iron hull in the marine environment.

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