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Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
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1

header2  

Science Conference Proceedings (OSTI)

LVF. **header2. **Ĺ*??H. uŇA*?0**}M^?*@ž…∑*np. M*ÚhŁ?*Ľ*? v??Ó??c Ň**-zv**. ?S÷*?*Ž?ůY?Ú≤Q?c7Q'??V ...

2008-05-30T23:59:59.000Z

2

Transportation, Aging and Disposal Canister System Performance...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1...

3

Disposable telemetry cable deployment system  

DOE Patents (OSTI)

A disposable telemetry cable deployment system for facilitating information retrieval while drilling a well includes a cable spool adapted for insertion into a drill string and an unarmored fiber optic cable spooled onto the spool cable and having a downhole end and a stinger end. Connected to the cable spool is a rigid stinger which extends through a kelly of the drilling apparatus. A data transmission device for transmitting data to a data acquisition system is disposed either within or on the upper end of the rigid stinger.

Holcomb, David Joseph (Sandia Park, NM)

2000-01-01T23:59:59.000Z

4

WIPP Home Page header  

NLE Websites -- All DOE Office Websites (Extended Search)

| News & Information | Document Center | Transportation | Opportunities | Contacts | Links | Search | News & Information | Document Center | Transportation | Opportunities | Contacts | Links | Search WWIS Public Inquiry Page Welcome to the WWIS Public Inquiry Page. This service is established in accordance an Agreement between the United States Department of Energy and the New Mexico Environment Department, dated February 11, 2005, Docket Number HWB 04-07 (CO). This service provides a replicate of information stored on the WIPP Waste Information System. Container Data will be available 14 days after emplacement in the WIPP Repository. The last update was Saturday, January 11, 2014 1:17:12 AM . You can find instructions for using this service by selecting the "Instructions" option. Information is available for disposed containers of transuranic (TRU) waste.

5

Method for improving the steam splits in a multiple steam injection process using multiple steam headers  

SciTech Connect

This patent describes a method for enhancing the uniformity of steam distribution in a multiple steam injection system comprising a steam generator, a primary steam header, at least one secondary steam header, a primary steam line connecting the generator to the primary header, at lease one secondary steam line connecting the primary header to the secondary steam header, and a plurality of tertiary steam lines connecting the secondary steam header to a plurality of stem injection wells. It comprises injecting a surfactant into the primary steam line, mixing the surfactant and steam in the primary steam line sufficiently so that the surfactant and the steam enter the primary steam header as a foam, and mixing the surfactant and steam in the secondary steam lines sufficiently so that the surfactant and the steam enter the secondary steam header as a foam.

Stowe, G.R.

1991-03-19T23:59:59.000Z

6

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR ...  

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR FUEL ASSEMBLIES United States Patent Application

7

Generic Disposal System Modeling, Fiscal Year 2011 Progress Report |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal System Modeling, Fiscal Year 2011 Progress Report Disposal System Modeling, Fiscal Year 2011 Progress Report Generic Disposal System Modeling, Fiscal Year 2011 Progress Report The UFD Campaign is developing generic disposal system models (GDSM) of different disposal environments and waste form options. Currently, the GDSM team is investigating four main disposal environment options: mined repositories in three geologic media (salt, clay, and granite) and the deep borehole concept in crystalline rock (DOE 2010d). Further developed the individual generic disposal system (GDS) models for salt, granite, clay, and deep borehole disposal environments. GenericDisposalSystModelFY11.pdf More Documents & Publications Integration of EBS Models with Generic Disposal System Models TSPA Model Development and Sensitivity Analysis of Processes Affecting

8

Transportation, Aging and Disposal Canister System Performance Specification: Revision 1  

Energy.gov (U.S. Department of Energy (DOE))

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system.

9

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

Turbo Machinery FACT SHEET (42646) Oct. 2006 I. PROJECT PARTICIPANTS A. Siemens Power Generation, Inc. B. Florida Turbine Technologies, Inc. C. Clean Energy Systems, Inc....

10

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

E. F. Loros

2000-06-30T23:59:59.000Z

11

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

42648 - Micro-Mixing Lean Premix Systems for Ultra-Low Emission 42648 - Micro-Mixing Lean Premix Systems for Ultra-Low Emission Hydrogen/Syngas Combustion 12/15/2006 FACT SHEET I. PROJECT PARTICIPANTS Parker Hannifin Corporation (Lead) Gas Turbine Fuel Systems Division, 9200 Tyler Blvd., Mentor OH 44060 PI: Dr. Adel Mansour (e-mail: amansour@parker.com, Ph.: 440-954-8171) University of California at Irvine UCI Combustion Laboratory, Irvine, CA 92617 Solar Turbines Incorporated 2200 Pacific Highway, San Diego CA 92101 II. PROJECT DESCRIPTION A. Objective(s) The overall objective of this DOE-Supported research and development program is to develop and test a next-generation, practical and scalable, high-performing, multi-point injector module for hydrogen and syngas fuels. The injector will use Parker Hannifin's

12

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

Shock Wave Compression rev060908, 6/14/06, rev 9/8/06 Shock Wave Compression rev060908, 6/14/06, rev 9/8/06 FACT SHEET Rampressor Shock Wave Compressor , DE-FC26-06NT42651 (Ramgen Power Systems, RPS) I. PROJECT PARTICIPANTS A. Prime Participant: Ramgen Power Systems, Inc (RPS) under cooperative Agreement DE-FC26-06NT42651 B. Sub-Award Participants: ASE Technologies (ASE), Manufacturing Resources Inc. (MRI), Geminus Technologies Development (GTD), Steve Kushnick, P.E., Alouette Technology. II. PROJECT DESCRIPTION A. Objective(s): Based on aerospace ramjet technology, Ramgen Power Systems is developing a novel more cost effective compressor concepts (air and carbon dioxide) for support of coal fueled gasification stationary power applications and for potential replacement of the compressor component in gas turbines.

13

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

5NT42646 Zero Emissions Coal Syngas-Oxygen Turbo Machinery 5NT42646 Zero Emissions Coal Syngas-Oxygen Turbo Machinery FACT SHEET (42646) Oct. 2006 I. PROJECT PARTICIPANTS A. Siemens Power Generation, Inc. B. Florida Turbine Technologies, Inc. C. Clean Energy Systems, Inc. II. PROJECT DESCRIPTION A. Objective(s) - To develop a cost effective and highly efficient turbo machinery system that will work with an oxy-fuel combustor that generates very high temperature CO2 and steam mixture as the working fluid. After expansion of the working fluid, the CO2 is captured allowing near-zero emissions of NOx and carbon. The project will complete conceptual designs of alternate steam cycles and select one cycle for detailed design based on cost and feasibility studies. B. Relevancy - 1. Background: CES, Inc. has an operational oxy-fuel combustor that generates

14

Defense High Level Waste Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents.

N. E. Pettit

2001-07-13T23:59:59.000Z

15

Disposal Systems Evaluations and Tool Development - Engineered...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

... 156 Table 5-5 Fuel cycle, disposal environment, and aging time for 24 base case combinations. ......

16

Defense High Level Waste Disposal Container System Description  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

17

Disposal Systems Evaluations and Tool Development - Engineered...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

disposable, plastic transfer pipettes. Sample vials were then filled with 40 mL of 2% nitric acid solutions (TraceSelect grade) in order to facilitate U(VI) desorption from...

18

Disposal Systems Evaluations and Tool Development - Engineered Barrier  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal Systems Evaluations and Tool Development - Engineered Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation The engineered barrier system (EBS) plays a key role in the long-term isolation of nuclear waste in geological repository environments. This report focuses on the progress made in the evaluation of EBS design concepts, assessment of clay phase stability at repository-relevant conditions, thermodynamic database development for cement and clay phases, and THMC coupled phenomena along with the development of tools and methods to examine these processes. This report also documents the advancements of the Disposal System Evaluation Framework (DSEF) for the development of

19

Integration of EBS Models with Generic Disposal System Models | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the Used Fuel Disposition campaign. This report addresses: predictive model capability for used nuclear fuel degradation based on electrochemical and thermodynamic principles, radiolysis model to evaluate the U(VI)-H2O-CO2 system, steps towards the evaluation of uranium alteration products, discussion of instant release fraction (IRF) of radionuclides from the nuclear fuel, and

20

Integration of EBS Models with Generic Disposal System Models | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the Used Fuel Disposition campaign. This report addresses: predictive model capability for used nuclear fuel degradation based on electrochemical and thermodynamic principles, radiolysis model to evaluate the U(VI)-H2O-CO2 system, steps towards the evaluation of uranium alteration products, discussion of instant release fraction (IRF) of radionuclides from the nuclear fuel, and

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Template:GeothermalHeader | Open Energy Information  

Open Energy Info (EERE)

of the page, which features a unique orange color scheme and simple menu. Parameters none Usage It should be called in the following format: GeothermalHeader Example This...

22

Naval Spent Nuclear Fuel disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

N. E. Pettit

2001-07-13T23:59:59.000Z

23

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

24

Preliminary Transportation, Aging and Disposal Canister System Performance Specification  

SciTech Connect

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2. The TAD canister, in conjunction with specialized overpacks will accomplish a number of functions in the management and disposal of spent nuclear fuel. Some of these functions will be accomplished at purchaser sites where commercial spent nuclear fuel (CSNF) is stored, and some will be performed within the Office of Civilian Radioactive Waste Management (OCRWM) transportation and disposal system. This document contains only those requirements unique to applications within Department of Energy's (DOE's) system. DOE recognizes that TAD canisters may have to perform similar functions at purchaser sites. Requirements to meet reactor functions, such as on-site dry storage, handling, and loading for transportation, are expected to be similar to commercially available canister-based systems. This document is intended to be referenced in the license application for the Monitored Geologic Repository (MGR). As such, the requirements cited herein are needed for TAD system use in OCRWM's disposal system. This document contains specifications for the TAD canister, transportation overpack and aging overpack. The remaining components and equipment that are unique to the OCRWM system or for similar purchaser applications will be supplied by others.

C.A Kouts

2006-11-22T23:59:59.000Z

25

System for disposing of radioactive water  

DOE Patents (OSTI)

A system for reducing radioactivity released to the biosphere in the course of producing natural gas from a reservoir stimulated by the detonation of nuclear explosives therein. Tritiated water produced with the gas is separated out and returned to a nuclear chimney through a string of tubing positioned within the well casing. The tubing string is positioned within the well casing in a manner which enhances separation of the water out of the gas and minimizes entrainment of water into the gas flowing out of the chimney.

Gotchy, Reginald L. (Bethesda, MD)

1976-01-13T23:59:59.000Z

26

Mobility Header Home Agent Switch Message  

E-Print Network (OSTI)

This document specifies an Internet standards track protocol for the Internet community, and requests discussion and suggestions for improvements. Please refer to the current edition of the "Internet Official Protocol Standards " (STD 1) for the standardization state and status of this protocol. Distribution of this memo is unlimited. This document specifies a new Mobility Header message type that can be used between a home agent and mobile node to signal to a mobile

B. Haley; V. Devarapalli; H. Deng; J. Kempf

2008-01-01T23:59:59.000Z

27

Thermodynamic data management system for nuclear waste disposal performance assessment  

Science Conference Proceedings (OSTI)

Thermodynamic property values for use in assessing the performance of a nuclear waste repository are described. More emphasis is on a computerized data base management system which facilitates use of the thermodynamic data in sensitivity analysis and other studies which critically assess the performance of disposal sites. Examples are given of critical evaluation procedures; comparison of apparent equilibrium constants calculated from the data base, with other work; and of correlations useful in estimating missing values of both free energy and enthalpy of formation for aqueous species. 49 refs., 11 figs., 6 tabs.

Phillips, S.L.; Hale, F.V.; Siegel, M.D.

1988-04-01T23:59:59.000Z

28

A Systems Study on How to Dispose of Fleets of Small Satellites  

E-Print Network (OSTI)

A Systems Study on How to Dispose of Fleets of Small Satellites Jason M. Andringa and Daniel E Systems Laboratory2 #12;Jason Andringa MIT Space Systems Laboratory3 A Systems Study on How to Dispose in Aeronautics and Astronautics Abstract A systems study was conducted to determine the most mass

29

Automated Monitoring System for Waste Disposal Sites and Groundwater  

Science Conference Proceedings (OSTI)

A proposal submitted to the U.S. Department of Energy (DOE), Office of Science and Technology, Accelerated Site Technology Deployment (ASTD) program to deploy an automated monitoring system for waste disposal sites and groundwater, herein referred to as the ''Automated Monitoring System,'' was funded in fiscal year (FY) 2002. This two-year project included three parts: (1) deployment of cellular telephone modems on existing dataloggers, (2) development of a data management system, and (3) development of Internet accessibility. The proposed concept was initially (in FY 2002) to deploy cellular telephone modems on existing dataloggers and partially develop the data management system at the Nevada Test Site (NTS). This initial effort included both Bechtel Nevada (BN) and the Desert Research Institute (DRI). The following year (FY 2003), cellular modems were to be similarly deployed at Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL), and the early data management system developed at the NTS was to be brought to those locations for site-specific development and use. Also in FY 2003, additional site-specific development of the complete system was to be conducted at the NTS. To complete the project, certain data, depending on site-specific conditions or restrictions involving distribution of data, were to made available through the Internet via the DRI/Western Region Climate Center (WRCC) WEABASE platform. If the complete project had been implemented, the system schematic would have looked like the figure on the following page.

S. E. Rawlinson

2003-03-01T23:59:59.000Z

30

Generic Disposal System Modeling--Fiscal Year 2011 Progress Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

12/2011 12/2011 Rev. 2 FCRD- T10-201 0-00005 FCRD Technical Integration Office (TIO) DOCUMENT NUMBER REQUEST TRANSMITTAL SHEET 1. Document Information Document Title/Description: Generic Disposal System Modeling--Fiscal Year 2011 Revision: 0 Progress Re~ort Assigned Document Number: FCRD-USED-2011-000184 Effective Start Date: 08/1112011 Document Author/Creator: D. Clayton, G. Freeze, T. Hadgu, E. Hardin, J. Lee, OR .~: J. Prouty, R. Rogers, W.M. Nutt, J. Berkholzer, H.H. Liu, L. Zheng, S. Chu Document Owner: Palmer Vaughn Date Range: Originating Organization: Sandia National Laboratories From: To: Milestone OM1 ~M2 OM3 ~M4 o Not a Milestone Milestone Number:: M21UF034101 and M41UF035102 Work Package WBS Number: FTSN11 UF0341 and FTSN11 UF0351; 1.02.08.03 Controlled Unclassified Infonnation (CUI) Type ~ None OOUO OAT o Other FCRD SYSTEM: Year: o FUEL Fuels 2011 OINTL International

31

Disposal Systems Evaluations and Tool Development - Engineered Barrier System Evaluation (Work Package LL1015080425)  

SciTech Connect

The Disposal Systems Evaluation Framework (DSEF) will use a logical process for developing one or more disposal system concepts (also referred to as repository system in this report) for any given waste form and geologic setting combination. In the Features, Events, and Processes (FEPs) group of work packages, there are seven categories of waste forms and eight categories of geologic setting being studied. The DSEF will also establish a Used Fuel Disposition Campaign (UFDC) knowledge management system to organize high-level information, data, and assumptions, thereby facilitating consistency in high-level system simulation and economic analyses. This system likely will be housed with the INL-based documentation system. Attention is given to lessons oearned from the systems used at the Waste Isolation Pilot Plant (WIPP) and the Yucca Mountain Project (YMP). Where reference material from other programs (e.g., international) is used or cited, the knowledge-management system imports the reference material directly or refer to it in bibliography form. Alternative data sets (e.g., from other programs) will also be utilized to evaluate their influence on DSEF analyses for given waste form and disposal-system combinations. The knowledge-management system can also be used to maintain the results of DSEF realizations, enabling the comparison and ranking of various waste-form/disposal-system-environment/disposal-system-design options. Finally, the UFDC knowledge-management system will be able to provide a compendium of 'templates' that can be utilized, in a labor-efficient fashion, to build parallel DSEF analyses (e.g., 'one offs'). The DSEF will not be a stand-alone, push-the-button and wait for the results, item of software. it will use osftware (probably EXCEL, initially), to guide the team members through a logical process of evaluating combinations of waste-form, disposal-syste-environment, and disposal-system design. In later stages, it will utilize software developed in the field of knowledge engineering and knowledge-management systems (Umeki et al. 2009). At certain points in the logical process, the DSEF software will point the evaluate to other software tools to do analyses needed to move the process forward. In the development of the DSEF, they will be mindful to make it no more complex than necessary to evaluate the system being considered. The DSEF will organize and document the work such that multiple realizations for different combinations can be compared and contrasted.

Blink, J A; Buscheck, T A; Halsey, W G; Wolery, T

2010-03-19T23:59:59.000Z

32

Transient Behaviour and Helium Discharge in Cryogenic Distribution Line (QRL) Headers Following Breakdown of Insulation Vacuum  

E-Print Network (OSTI)

Transient Behaviour and Helium Discharge in Cryogenic Distribution Line (QRL) Headers Following Breakdown of Insulation Vacuum

Chorowski, M

1997-01-01T23:59:59.000Z

33

Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.  

SciTech Connect

Key components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate long-term repository performance. The focus of this report is the following: (1) Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept; (2) Evaluation of key parameters in the characterization of EBS performance; (3) Identification of key knowledge gaps and uncertainties; and (4) Evaluation of tools and modeling approaches for EBS processes and performance. The above topics will be evaluated through the analysis of the following: (1) Overview of EBS concepts for various NW disposal systems; (2) Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments; (3) Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS; and (4) Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

Rutqvist, Jonny (LBNL); Liu, Hui-Hai (LBNL); Steefel, Carl I. (LBNL); Serrano de Caro, M. A. (LLNL); Caporuscio, Florie Andre (LANL); Birkholzer, Jens T. (LBNL); Blink, James A. (LLNL); Sutton, Mark A. (LLNL); Xu, Hongwu (LANL); Buscheck, Thomas A. (LLNL); Levy, Schon S. (LANL); Tsang, Chin-Fu (LBNL); Sonnenthal, Eric (LBNL); Halsey, William G. (LLNL); Jove-Colon, Carlos F.; Wolery, Thomas J. (LLNL)

2011-01-01T23:59:59.000Z

34

Modelling the upgrade of an urban waste disposal system  

Science Conference Proceedings (OSTI)

The waste intermodal station of Clyde, in the city of Sydney, Australia, is in the heart of a complex network of terminals connected by road and rail to transport urban waste from its first collection to its final disposal. The amount of waste the network ... Keywords: Discrete-event simulation, Intermodal transfer, Satellite stations, Urban solid waste, Waste collection

G. Guariso; F. Michetti; F. Porta; S. Moore

2009-11-01T23:59:59.000Z

35

Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal Systems Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation (FCRD-USED-2011-000132) Prepared for U.S. Department of Energy Used Fuel Disposition Campaign Carlos F. Jové Colón (SNL) Florie A. Caporuscio, Schön S. Levy (LANL) Mark Sutton, James A. Blink, Harris R. Greenberg, Massimiliano Fratoni, William G. Halsey, Thomas J. Wolery (LLNL) Jonny Rutqvist, Carl I. Steefel, Juan Galindez, Jens Birkholzer, Hui-Hai Liu, (LBNL) June 15 th , 2011 SAND2011-4335 P Prepared by: Sandia National Laboratories Albuquerque, New Mexico 87185 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of

36

Tank waste remediation system retrieval and disposal mission waste feed delivery plan  

Science Conference Proceedings (OSTI)

This document is a plan presenting the objectives, organization, and management and technical approaches for the Waste Feed Delivery (WFD) Program. This WFD Plan focuses on the Tank Waste Remediation System (TWRS) Project`s Waste Retrieval and Disposal Mission.

Potter, R.D.

1998-01-08T23:59:59.000Z

37

Water Well Data Elements Well Header Tab Page  

E-Print Network (OSTI)

Water producing from Lithologic formation from which water is produced. at depth Top of water producing formation (ft) to Base of water producing formation (ft) Static water level Static water level below casingWater Well Data Elements Well Header Tab Page: This list contains location and identification

Frank, Thomas D.

38

Adaptive Header Compression for Wireless Networks Changli Jiao  

E-Print Network (OSTI)

Adaptive Header Compression for Wireless Networks Changli Jiao Department of Electrical without compression. From the standpoint of the communication medium, the channel usage will be improved at a lower speed if the gap between ACKs is too big. This will have two side results. First, the efficiency

Richard III, Golden G.

39

Tank waste remediation system retrieval and disposal mission initial updated baseline summary  

Science Conference Proceedings (OSTI)

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor`s Readiness-to-Proceed in support of the Phase 1B mission.

Swita, W.R.

1998-01-05T23:59:59.000Z

40

Development of Methods to Repair Header Stub Tube Bends  

Science Conference Proceedings (OSTI)

Repair of flow-accelerated corrosion damage in bent header stub tubes in heat recovery steam generators (HRSGs) is normally accomplished by spreading tubing pendants to gain access, cutting your way in and welding your way out, or plugging damaged tubing. The technology described in this report is being developed to enable the replacement of damaged tubing in a method that will dramatically reduce change-out time in the event of a failure.

2008-12-23T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Perspectives on integrating the US radioactive waste disposal system  

SciTech Connect

The waste management systems being developed and deployed by the DOE Office of Civilian Radioactive Waste Management (OCRWM) is large, complex, decentralized, and long term. As a result, a systems integration approach has been implemented by OCRWM. The fundamentals of systems integration and its application are examined in the context of the OCRWM program. This application is commendable, and some additional systems integration features are suggested to enhance its benefits. 6 refs., 1 fig.

Culler, F.L. (Electric Power Research Inst., Palo Alto, CA (USA)); Croff, A.G. (Oak Ridge National Lab., TN (USA))

1990-01-01T23:59:59.000Z

42

Explosive destruction system for disposal of chemical munitions  

DOE Patents (OSTI)

An explosive destruction system and method for safely destroying explosively configured chemical munitions. The system comprises a sealable, gas-tight explosive containment vessel, a fragment suppression system positioned in said vessel, and shaped charge means for accessing the interior of the munition when the munition is placed within the vessel and fragment suppression system. Also provided is a means for treatment and neutralization of the munition's chemical fills, and means for heating and agitating the contents of the vessel. The system is portable, rapidly deployable and provides the capability of explosively destroying and detoxifying chemical munitions within a gas-tight enclosure so that there is no venting of toxic or hazardous chemicals during detonation.

Tschritter, Kenneth L. (Livermore, CA); Haroldsen, Brent L. (Manteca, CA); Shepodd, Timothy J. (Livermore, CA); Stofleth, Jerome H. (Albuquerque, NM); DiBerardo, Raymond A. (Baltimore, MD)

2005-04-19T23:59:59.000Z

43

Explosive destruction system for disposal of chemical munitions  

SciTech Connect

An explosive destruction system and method for safely destroying explosively configured chemical munitions. The system comprises a sealable, gas-tight explosive containment vessel, a fragment suppression system positioned in said vessel, and shaped charge means for accessing the interior of the munition when the munition is placed within the vessel and fragment suppression system. Also provided is a means for treatment and neutralization of the munition's chemical fills, and means for heating and agitating the contents of the vessel. The system is portable, rapidly deployable and provides the capability of explosively destroying and detoxifying chemical munitions within a gas-tight enclosure so that there is no venting of toxic or hazardous chemicals during detonation.

Tschritter, Kenneth L. (Livermore, CA); Haroldsen, Brent L. (Manteca, CA); Shepodd, Timothy J. (Livermore, CA); Stofleth, Jerome H. (Albuquerque, NM); DiBerardo, Raymond A. (Baltimore, MD)

2005-04-19T23:59:59.000Z

44

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description  

SciTech Connect

This document is prepared in order to support the US Department of Energy`s evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors.

McLaughlin, T.J.

1998-01-06T23:59:59.000Z

45

By-product disposal from MSW incinerator flue gas cleaning systems  

Science Conference Proceedings (OSTI)

Waste incineration has been found to be an effective method of achieving significant volume reduction of Municipal Solid Waste (MSW) while at the same time allowing for energy recovery in the form of steam or electricity. Concern over potential air pollution from incinerators in the form of acid gases, heavy metals and dioxins has led to the application of Spray Dryer Absorption (SDA) flue gas cleaning systems to control these emissions. SDA has demonstrated high efficiencies in converting these air pollutants into a dry by-product for disposal. This has, in turn, led to concerns over potential secondary pollution from the disposal of these by-products. This paper presents a description of the SDA process and reviews disposal options for the SDA product. Product characteristics are given and results of leaching studies are presented. Comparisons between EPA's and TEP and TCLP procedures are presented. Results of dioxin measurements from the by-product are given.

Donnelly, J.R. (Joy Manufacturing Co., Los Angeles, CA (US)); Jons, E. (A/S Niro Atomizer, Copenhagen (DK))

1987-01-01T23:59:59.000Z

46

Discussions on Disposal Forms of Auxiliary Heat Source in Surface Water Heat Pump System  

E-Print Network (OSTI)

This paper presents two common forms of auxiliary heat source in surface water heat pump system and puts forward the idea that the disposal forms affect operation cost. It deduces operation cost per hour of the two forms. With a project calculation, it illuminates that the post-located auxiliary heat source cheaper and superior to the fore-located one.

Qian, J.; Sun, D.; Li, X.; Li, G.

2006-01-01T23:59:59.000Z

47

Dissolved Gas Analysis (DGA) by EPRI Disposable Oil Sampling System (EDOSS)  

Science Conference Proceedings (OSTI)

The utility industry has increasingly applied dissolved gas analysis (DGA) to assess the condition of fluid-filled equipment. Modifications to the EPRI Pressurized Oil Sampling System (EPOSS), a novel DGA method developed in 1983, have rendered the system more cost-effective without compromising its accuracy and precision. Designated the EPRI Disposable Oil Sampling System, EDOSS safely operates with all types of fluid-filled equipment under most weather conditions.

1998-10-12T23:59:59.000Z

48

Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses  

SciTech Connect

This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

1994-08-01T23:59:59.000Z

49

Disposable rabbit  

DOE Patents (OSTI)

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, Leroy C. (Idaho Falls, ID); Trammell, David R. (Rigby, ID)

1986-01-01T23:59:59.000Z

50

Disposal rabbit  

DOE Patents (OSTI)

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, L.C.; Trammell, D.R.

1983-10-12T23:59:59.000Z

51

Navy explosive ordnance disposal project: Optical ordnance system development. Final report  

SciTech Connect

An optical ordnance firing system consisting of a portable hand held solid state rod laser and an optically ignited detonator has been developed for use in explosive ordnance disposal (EOD) activities. Solid state rod laser systems designed to have an output of 150 mJ in a 500 microsecond pulse have been produced and evaluated. A laser ignited detonator containing no primary explosives has been designed and fabricated. The detonator has the same functional output as an electrically fired blasting cap. The optical ordnance firing system has demonstrated the ability to reliably detonate Comp C-4 through 1000 meters of optical fiber.

Merson, J.A.; Salas, F.J.; Helsel, F.M.

1996-03-01T23:59:59.000Z

52

Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) System Configuration Management Plan  

Science Conference Proceedings (OSTI)

The Treated Effluent Disposal Facility Operator Training Station (TEDF OTS) is a computer based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS). It consists of PC compatible computers and a Programmable Logic Controller (PLC) designed to emulate the responses of various plant components connected to or under the control of the CCS. The system trains operators by simulating the normal operation but also has the ability to force failures of different equipment allowing the operator to react and observe the events. The paper describes organization, responsibilities, system configuration management activities, software, and action plans for fully utilizing the simulation program.

Carter, R.L. Jr.

1994-06-01T23:59:59.000Z

53

U-134: Apache Traffic Server Host Header Processing Flaw Lets Remote Users  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4: Apache Traffic Server Host Header Processing Flaw Lets 4: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service U-134: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service March 27, 2012 - 7:00am Addthis PROBLEM: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service PLATFORM: Versions prior to 3.0.4 and 3.1.3 ABSTRACT: A vulnerability was reported in Apache Traffic Server. A remote user can cause denial of service conditions. reference LINKS: SecurityTracker Alert ID: 1026847 CVE-2012-0256 Secunia Advisory SA48509 IMPACT ASSESSMENT: High Discussion: A remote user can send a request with a specially crafted 'Host' header value to trigger a heap allocation error and cause the target service to crash. Impact: A remote user can cause the target service to crash.

54

U-134: Apache Traffic Server Host Header Processing Flaw Lets Remote Users  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

34: Apache Traffic Server Host Header Processing Flaw Lets 34: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service U-134: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service March 27, 2012 - 7:00am Addthis PROBLEM: Apache Traffic Server Host Header Processing Flaw Lets Remote Users Deny Service PLATFORM: Versions prior to 3.0.4 and 3.1.3 ABSTRACT: A vulnerability was reported in Apache Traffic Server. A remote user can cause denial of service conditions. reference LINKS: SecurityTracker Alert ID: 1026847 CVE-2012-0256 Secunia Advisory SA48509 IMPACT ASSESSMENT: High Discussion: A remote user can send a request with a specially crafted 'Host' header value to trigger a heap allocation error and cause the target service to crash. Impact: A remote user can cause the target service to crash.

55

Determining the Cause of a Header Failure in a Natural Gas Production Facility  

SciTech Connect

An investigation was made into the premature failure of a gas-header at the Rocky Mountain Oilfield Testing Center (RMOTC) natural gas production facility. A wide variety of possible failure mechanisms were considered: design of the header, deviation from normal pipe alloy composition, physical orientation of the header, gas composition and flow rate, type of corrosion, protectiveness of the interior oxide film, time of wetness, and erosion-corrosion. The failed header was examined using metallographic techniques, scanning electron microscopy, and microanalysis. A comparison of the failure site and an analogous site that had not failed, but exhibited similar metal thinning was also performed. From these studies it was concluded that failure resulted from erosion-corrosion, and that design elements of the header and orientation with respect to gas flow contributed to the mass loss at the failure point.

Matthes, S.A.; Covino, B.S., Jr.; Bullard, S.J.; Ziomek-Moroz, M.; Holcomb, G.R.

2007-03-01T23:59:59.000Z

56

Pyrolysis of epoxies used for thermal-battery headers  

DOE Green Energy (OSTI)

Thermally activated batteries use an epoxy for encapsulation of the electrical feedthroughs in the header of the battery. When the thermal battery is thermally abused, the encapsulant can pyrolyze and generate large internal pressures. This causes the battery to vent in extreme cases. The nature of these gases has never been adequately documented. Therefore, a study was undertaken to address this deficiency. The pyrolysis of various encapsulants that have been used, or are being considered for use, in thermally activated batteries was studied over a temperature range of 155 to 455 C. The composition of the pyrolysis decomposition products was determined by gas chromatography/mass spectrometry (GS/MS). This determination is helpful in assessing the potential environmental and health effect for personnel exposed to such gases. In addition, the thermal stability of the various epoxies was measured by thermogravimetric analysis (TGA).

Guidotti, R.A.; Thornberg, S.M.; Campbell-Domme, B.

1995-08-01T23:59:59.000Z

57

Preliminary Systems Design Study assessment report. Volume 5, Land disposal compliance and hydrogen generation restricted concepts  

SciTech Connect

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept.

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1991-11-01T23:59:59.000Z

58

Tank waste remediation system retrieval and disposal mission initial updated baseline summary  

SciTech Connect

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors` operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors` facilities.

Swita, W.R.

1998-01-09T23:59:59.000Z

59

PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED 2. Section 2. Test Results T-641317  

SciTech Connect

ABS>A test was made on the Radioactive Waste Disposal (RWD) system to determine the acceptability of procedures used in containing, processing, and disposing the wastes received from the plant during a steady-state operation. The RWD system was found to be adequate and to have 60,000 gallons available at all times in the Surge and Decay tanks for safety injection. (D.L.C.)

1961-03-17T23:59:59.000Z

60

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foaming Options · Compressed Air Foam Systems (CAFS) · Foam Blower · Foam Generator · Nozzle Systems #12;Disposal: Science and Theory Compressed ­ Industry owned response team #12;Disposal: Science and Theory Commercial CAFS for Poultry · Poultry

Benson, Eric R.

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Use of depleted uranium metal as cask shielding in high-level waste storage, transport, and disposal systems  

SciTech Connect

The US DOE has amassed over 555,000 metric tons of depleted uranium from its uranium enrichment operations. Rather than dispose of this depleted uranium as waste, this study explores a beneficial use of depleted uranium as metal shielding in casks designed to contain canisters of vitrified high-level waste. Two high-level waste storage, transport, and disposal shielded cask systems are analyzed. The first system employs a shielded storage and disposal cask having a separate reusable transportation overpack. The second system employs a shielded combined storage, transport, and disposal cask. Conceptual cask designs that hold 1, 3, 4 and 7 high-level waste canisters are described for both systems. In all cases, cask design feasibility was established and analyses indicate that these casks meet applicable thermal, structural, shielding, and contact-handled requirements. Depleted uranium metal casting, fabrication, environmental, and radiation compatibility considerations are discussed and found to pose no serious implementation problems. About one-fourth of the depleted uranium inventory would be used to produce the casks required to store and dispose of the nearly 15,400 high-level waste canisters that would be produced. This study estimates the total-system cost for the preferred 7-canister storage and disposal configuration having a separate transportation overpack would be $6.3 billion. When credits are taken for depleted uranium disposal cost, a cost that would be avoided if depleted uranium were used as cask shielding material rather than disposed of as waste, total system net costs are between $3.8 billion and $5.5 billion.

Yoshimura, H.R.; Ludwigsen, J.S.; McAllaster, M.E. [and others

1996-09-01T23:59:59.000Z

62

Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

performance cleanup closure performance cleanup closure M E Environmental Management Environmental Management Performance Assessment Community of Practice Technical Exchange July 13-14, 2009 Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal - Overview and Focused Discussions David S. Kosson CRESP and Vanderbilt University Tank Waste Corporate Board Meeting July 29, 2009 1 safety performance cleanup closure M E Environmental Management Environmental Management Agenda * Overview of DOE Performance Assessment Practices * Focused Discussions - Role of PA Process in Risk Communication and Decisions - Modeling Improvements - PA Assumption Validation - Uncertainty Evaluation - Evolving EPA Developments - Related IAEA Activities * Looking forward

63

State-of-the-art of liquid waste disposal for geothermal energy systems: 1979. Report PNL-2404  

SciTech Connect

The state-of-the-art of geothermal liquid waste disposal is reviewed and surface and subsurface disposal methods are evaluated with respect to technical, economic, legal, and environmental factors. Three disposal techniques are currently in use at numerous geothermal sites around the world: direct discharge into surface waters; deep-well injection; and ponding for evaporation. The review shows that effluents are directly discharged into surface waters at Wairakei, New Zealand; Larderello, Italy; and Ahuachapan, El Salvador. Ponding for evaporation is employed at Cerro Prieto, Mexico. Deep-well injection is being practiced at Larderello; Ahuachapan; Otake and Hatchobaru, Japan; and at The Geysers in California. All sites except Ahuachapan (which is injecting only 30% of total plant flow) have reported difficulties with their systems. Disposal techniques used in related industries are also reviewed. The oil industry's efforts at disposal of large quantities of liquid effluents have been quite successful as long as the effluents have been treated prior to injection. This study has determined that seven liquid disposal methods - four surface and three subsurface - are viable options for use in the geothermal energy industry. However, additional research and development is needed to reduce the uncertainties and to minimize the adverse environmental impacts of disposal. (MHR)

Defferding, L.J.

1980-06-01T23:59:59.000Z

64

State-of-the-art of liquid waste disposal for geothermal energy systems: 1979. Report PNL-2404  

DOE Green Energy (OSTI)

The state-of-the-art of geothermal liquid waste disposal is reviewed and surface and subsurface disposal methods are evaluated with respect to technical, economic, legal, and environmental factors. Three disposal techniques are currently in use at numerous geothermal sites around the world: direct discharge into surface waters; deep-well injection; and ponding for evaporation. The review shows that effluents are directly discharged into surface waters at Wairakei, New Zealand; Larderello, Italy; and Ahuachapan, El Salvador. Ponding for evaporation is employed at Cerro Prieto, Mexico. Deep-well injection is being practiced at Larderello; Ahuachapan; Otake and Hatchobaru, Japan; and at The Geysers in California. All sites except Ahuachapan (which is injecting only 30% of total plant flow) have reported difficulties with their systems. Disposal techniques used in related industries are also reviewed. The oil industry's efforts at disposal of large quantities of liquid effluents have been quite successful as long as the effluents have been treated prior to injection. This study has determined that seven liquid disposal methods - four surface and three subsurface - are viable options for use in the geothermal energy industry. However, additional research and development is needed to reduce the uncertainties and to minimize the adverse environmental impacts of disposal. (MHR)

Defferding, L.J.

1980-06-01T23:59:59.000Z

65

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Brief History of Foam 2004 ­ Bud and foam 2009 ­ No advantage for gas #12;Disposal: Science and Theory What is foam? · What is fire fighting system. #12;Disposal: Science and Theory Foam Composition · Foam can include ­ Mixture of surfactants

Benson, Eric R.

66

Review of Fabrication and In-Service Performance of a Grade 91 Header  

Science Conference Proceedings (OSTI)

This report reviews the construction details of two retrofit Grade 91 headers installed in a UK power station in the 1990s. The report documents the design, manufacture, quality assurance, inspection, repair history, and results of postĖservice testing of the two headers. The report also summarizes the subsequent in-service inspection and repair history, where either published or available from the plant operator, covering the nondestructive evaluation (the type of technique used and extent of ...

2013-07-30T23:59:59.000Z

67

Waste heat recovery system having thermal sleeve support for heat pipe  

SciTech Connect

A system for recovering waste heat from a stream of heated gas is disclosed. The system includes a convection heat transfer chamber, a boiler tank, and a plurality of heat pipes thermally interconnecting the convection heat transfer chamber with the boiler tank. Each of the heat pipes includes an evaporator section which is disposed in heat transfer relation with a stream of heated gas flowing through the convection heat transfer chamber, and a condenser section disposed in heat transfer relation with a volume of water contained within the boiler tank. The boiler tank is provided with a header plate having an array of heat pipe openings through which the heat pipes project. A heat pipe support sleeve is received in each heat pipe opening in sealed engagement with the header plate, with the heat pipes projecting through the support sleeves and thermally interconnecting the convection heat transfer chamber with the boiler tank. An intermediate portion of each heat pipe is received in sealed engagement with its associated support sleeve. In a preferred embodiment, heat transfer through the support sleeve is minimized in an arrangement in which each heat pipe opening is reduced by a stepped bore with the support sleeve connected in threaded, sealed engagement with the stepped bore. Futhermore, in this arrangement, the support sleeve has swaged end portions which project beyond the header plate and engage the heat pipe on opposite sides at points which are remote with respect to the support sleeve/header plate interface. One of the swages end portions is sealed against the heat pipe in a fluid-tight union within the boiler tank. The support sleeve is radially spaced with respect to the heat pipe, and is also radially spaced with respect to the heat pipe opening whereby heat transfer through the walls of the heat pipe to the support sleeve and to the header plate is minimized by concentric annular air gaps.

McCurley, J.

1984-01-24T23:59:59.000Z

68

Waste heat recovery system having thermal sleeve support for heat pipe  

SciTech Connect

A system for recovering waste heat from a stream of heated gas is disclosed. The system includes a convection heat transfer chamber, a boiler tank, and a plurality of heat pipes thermally interconnecting the convection heat transfer chamber with the boiler tank. Each of the heat pipes includes an evaporator section which is disposed in heat transfer relation with a stream of heated gas flowing through the convection heat transfer chamber, and a condenser section disposed in heat transfer relation with a volume of water contained within the boiler tank. The boiler tank is provided with a header plate having an array of heat pipe openings through which the heat pipes project. A heat pipe support sleeve is received in each heat pipe opening in sealed engagement with the header plate, with the heat pipes projecting through the support sleeves and thermally interconnecting the convection heat transfer chamber with the boiler tank. An intermediate portion of each heat pipe is received in sealed engagement with its associated support sleeve. In a preferred embodiment, heat transfer through the support sleeve is minimized in an arrangement in which each heat pipe opening is reduced by a stepped bore with the support sleeve connected in threaded, sealed engagement with the stepped bore. Furthermore, in this arrangement, the support sleeve has swaged end portions which project beyond the header plate and engage the heat pipe on opposite sides at points which are remote with respect to the support sleeve/header plate interface. One of the swaged end portions is sealed against the heat pipe in a fluid-tight union within the boiler tank. The support sleeve is radially spaced with respect to the heat pipe, and is also radially spaced with respect to the heat pipe opening whereby heat transfer through the walls of the heat pipe to the support sleeve and to the header plate is minimized by concentric annular air gaps.

McCurley, J.

1984-04-10T23:59:59.000Z

69

Waste heat recovery system having thermal sleeve support for heat pipe  

SciTech Connect

A system for recovering waste heat from a stream of heated gas is disclosed. The system includes a convection heat transfer chamber, a boiler tank, and a plurality of heat pipes thermally interconnecting the convection heat transfer chamber with the boiler tank. Each of the heat pipes includes an evaporator section which is disposed in heat transfer relation with a stream of heated gas flowing through the convection heat transfer chamber, and a condenser section disposed in heat transfer relation with a volume of water contained within the boiler tank. The boiler tank is provided with a header plate having an array of heat pipe openings through which the heat pipes project. A heat pipe support sleeve is received in each heat pipe opening in sealed engagement with the header plate, with the heat pipes projecting through the support sleeves and thermally interconnecting the convection heat transfer chamber with the boiler tank. An intermediate portion of each heat pipe is received in sealed engagement with its associated support sleeve. In a preferred embodiment, heat transfer through the support sleeve is minimized in an arrangement in which each heat pipe opening is reduced by a stepped bore with the support sleeve connected in threaded, sealed engagement with the stepped bore. Furthermore, in this arrangement, the support sleeve has swaged end portions which project beyond the header plate and engage the heat pipe on opposite sides at points which are remote with respect to the support sleeve/header plate interface. One of the swaged end portions is sealed against the heat pipe in a fluid-tight union within the boiler tank. The support sleeve is radially spaced with respect to the heat pipe and is also radially spaced with respect to the heat pipe opening whereby heat transfer through the walls of the heat pipe to the support sleeve and to the header plate is minimized by concentric annular air gaps.

McCurley, J.

1984-12-04T23:59:59.000Z

70

Waste heat recovery system having thermal sleeve support for heat pipe  

SciTech Connect

A system for recovering waste heat from a stream of heated gas is disclosed. The system includes a convection heat transfer chamber, a boiler tank, and a plurality of heat pipes thermally interconnecting the convection heat transfer chamber with the boiler tank. Each of the heat pipes includes an evaporator section which is disposed in heat transfer relation with a stream of heated gas flowing through the convection heat transfer chamber, and a condenser section disposed in heat transfer relation with a volume of water contained within the boiler tank. The boiler tank is provided with a header plate having an array of heat pipe openings through which the heat pipes project. A heat support sleeve is received in each heat pipe opening in sealed engagement with the header plate, with the heat pipes projecting through the support sleeves and thermally interconnecting the convection heat transfer chamber with the boiler tank. An intermediate portion of each heat pipe is received in sealed engagement with its associated support sleeve. In a preferred embodiment, heat transfer through the support sleeve is minimized in an arrangement in which each heat pipe opening is reduced by a stepped bore with the support sleeve connected in threaded, sealed engagement with the stepped bore. Furthermore, in this arrangement, the support sleeve has swaged end portions which project beyond the header plate and engage the heat pipe on opposite sides at points which are remote with respect to the support sleeve/header plate interface. One of the swaged end portions is sealed against the heat pipe in a fluid-tight union within the boiler tank. The support sleeve is radially spaced with respect to the heat pipe, and is also radially spaced with respect to the heat pipe opening whereby heat transfer through the walls of the heat pipe to the support sleeve and to the header plate is minimized by concentric annular air gaps.

McCurley, J.

1984-12-18T23:59:59.000Z

71

An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities  

SciTech Connect

Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000ís of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

2011-03-01T23:59:59.000Z

72

Some logistical considerations in designing a system of deep boreholes for disposal of high-level radioactive waste.  

Science Conference Proceedings (OSTI)

Deep boreholes could be a relatively inexpensive, safe, and rapidly deployable strategy for disposing Americas nuclear waste. To study this approach, Sandia invested in a three year LDRD project entitled %E2%80%9CRadionuclide Transport from Deep Boreholes.%E2%80%9D In the first two years, the borehole reference design and backfill analysis were completed and the supporting modeling of borehole temperature and fluid transport profiles were done. In the third year, some of the logistics of implementing a deep borehole waste disposal system were considered. This report describes what was learned in the third year of the study and draws some conclusions about the potential bottlenecks of system implementation.

Gray, Genetha Anne; Brady, Patrick Vane [Sandia National Laboratories, Albuquerque, NM; Arnold, Bill Walter [Sandia National Laboratories, Albuquerque, NM

2012-09-01T23:59:59.000Z

73

Some logistical considerations in designing a system of deep boreholes for disposal of high-level radioactive waste.  

SciTech Connect

Deep boreholes could be a relatively inexpensive, safe, and rapidly deployable strategy for disposing Americas nuclear waste. To study this approach, Sandia invested in a three year LDRD project entitled %E2%80%9CRadionuclide Transport from Deep Boreholes.%E2%80%9D In the first two years, the borehole reference design and backfill analysis were completed and the supporting modeling of borehole temperature and fluid transport profiles were done. In the third year, some of the logistics of implementing a deep borehole waste disposal system were considered. This report describes what was learned in the third year of the study and draws some conclusions about the potential bottlenecks of system implementation.

Gray, Genetha Anne; Brady, Patrick Vane [Sandia National Laboratories, Albuquerque, NM; Arnold, Bill Walter [Sandia National Laboratories, Albuquerque, NM

2012-09-01T23:59:59.000Z

74

Lessons learned from reactive transport modeling of a low-activity waste glass disposal system  

Science Conference Proceedings (OSTI)

A set of reactive chemical transport calculations were conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal ... Keywords: chemical transport, low-level waste, numerical model, unsaturated flow, vadose zone

Diana H. Bacon; B. Peter McGrail

2003-04-01T23:59:59.000Z

75

Septage Disposal, Licensure (Montana)  

Energy.gov (U.S. Department of Energy (DOE))

This statute describes licensing requirements for septage disposal, and addresses land disposal and processing facilities.

76

IAEA Verification Experiment at the Portsmouth Gaseous Diffusion Plant: Report on the Cascade Header Enrichment Monitor  

SciTech Connect

The authors describe the Cascade Header Enrichment Monitor (CHEM) for the Portsmouth Gaseous Diffusion Plant at Piketon, Ohio, and present the calibration and measurement results. The US government has offered excess fissile material that is no longer needed for defense purposes for International Atomic Energy Agency (IAEA) inspection. Measurement results provided by the CHEM were used by the IAEA in a verification experiment to provide confidence that the US successfully blended excess highly enriched uranium (HEU) down to low enriched uranium (LEU). The CHEM measured the uranium enrichment in two cascade header pipes, a 20.32-cm HEU pipe and a 7.62-cm product LEU pipe. The CHEM determines the amount of {sup 235}U from the 185.7-keV gamma-ray photopeak and the amount of total uranium by x-ray fluorescence (XRF) of the 98.4-keV x-ray from uranium with a {sup 57}Co XRF source. The ratio yields the enrichment. The CHEM consists of a collimator assembly, an electromechanically cooled germanium detector, and a rack-mounted personal computer running commercial and custom software. The CHEM was installed in December 1997 and was used by the IAEA inspectors for announced and unannounced inspections on the HEU and LEU header pipes through October 1998. The equipment was sealed with tamper-indicating enclosures when the inspectors were not present.

P. L. Kerr; D. A. Close; W. S. Johnson; R. M. Kandarian; C. E. Moss; C. D. Romero

1999-03-01T23:59:59.000Z

77

Two-phase flow behavior inside a header connected to multiple parallel channels  

SciTech Connect

The main objective of this work is to examine the flow distribution of two-phase mixture to parallel channels and to investigate the flow behavior at header-channel junctions simulating the corresponding parts of compact heat exchangers. The cross-section of the header and the channels were fixed to 14 mm x 14 mm and 12 mm x 1.6 mm, respectively. The mass flux and the mass quality ranges were 70-165 kg/m{sup 2} s and 0.3-0.7, respectively. Air and water were used as the test fluids. The flow distribution at the fore part of the header (region A) is affected only by the upstream flow configuration and the rate of liquid flow separation decreased a flowing downwards. On the other hand, in the rear part, the downstream effect predominates over the upstream effect due to strong flow recirculation near the end plate. In this part, the liquid separation increased (region B) and then decreased (region C) as the mixture proceeds downwards. The validity of the existing models for branching flows at parallel T-junction was tested, and turned out to be appropriate for region A. However, the models were not applicable to the rear part due to a strong flow recirculation. Moreover, the effect of the membranes in channels was investigated, but that was minor. (author)

Lee, Jun Kyoung [School of Mechanical Engineering and Automation, Kyungnam University, Masan 631-701 (Korea)

2009-01-15T23:59:59.000Z

78

Headers will be added later Deriving groundwater estimates in Australia  

E-Print Network (OSTI)

and Steelhead Trout at Lower Granite Dam GENE M. MATTHEWS, GEORGE A. SWAN, and JIM ROSS SMITH ABSTRACT-A new trout, Salmo Gairdneri, at Lower Granite Dam on the lower Snake River is described. Major changes from area totally supplied by gravity-flow. The system is currently being evaluated by the National Marine

Tregoning, Paul

79

Header and Drum Damage: Theory and Practice: Volume 1: Information Common to All Damage Types; Volume 2: Mechanisms  

Science Conference Proceedings (OSTI)

Headers and drums represent two of the largest and most expensive components in boilers. Particularly in the case of high-temperature headers, there are considerable safety concerns when operating aging plants, and some notable failures have occurred. For these reasons, understanding the types of damage that can accumulate and dealing with that damage are vital to the safe and economic operation of fossil power plants.

2003-12-31T23:59:59.000Z

80

Vitrification of high level nuclear waste inside ambient temperature disposal containers using inductive heating: The SMILE system  

Science Conference Proceedings (OSTI)

A new approach, termed SMILE (Small Module Inductively Loaded Energy), for the vitrification of high level nuclear wastes (HLW) is described. Present vitrification systems liquefy the HLW solids and associated frit material in large high temperature melters. The molten mix is then poured into small ({approximately}1 m{sup 3}) disposal canisters, where it solidifies and cools. SMILE eliminates the separate, large high temperature melter. Instead, the BLW solids and frit melt inside the final disposal containers, using inductive heating. The contents then solidify and cool in place. The SMILE modules and the inductive heating process are designed so that the outer stainless can of the module remains at near ambient temperature during the process cycle. Module dimensions are similar to those of present disposal containers. The can is thermally insulated from the high temperature inner container by a thin layer of refractory alumina firebricks. The inner container is a graphite crucible lined with a dense alumina refractory that holds the HLW and fiit materials. After the SMILE module is loaded with a slurry of HLW and frit solids, an external multi-turn coil is energized with 30-cycle AC current. The enclosing external coil is the primary of a power transformer, with the graphite crucible acting as a single turn ``secondary.`` The induced current in the ``secondary`` heats the graphite, which in turn heats the HLW and frit materials. The first stage of the heating process is carried out at an intermediate temperature to drive off remnant liquid water and water of hydration, which takes about 1 day. The small fill/vent tube to the module is then sealed off and the interior temperature raised to the vitrification range, i.e., {approximately}1200C. Liquefaction is complete after approximately 1 day. The inductive heating then ceases and the module slowly loses heat to the environment, allowing the molten material to solidify and cool down to ambient temperature.

Powell, J.; Reich, M.; Barletta, R.

1996-03-01T23:59:59.000Z

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We encourage you to perform a real-time search of NLEBeta
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81

Submergible barge retrievable storage and permanent disposal system for radioactive waste  

DOE Patents (OSTI)

A submergible barge and process for submerging and storing radioactive waste material along a seabed. A submergible barge receives individual packages of radwaste within segregated cells. The cells are formed integrally within the barge, preferably surrounded by reinforced concrete. The cells are individually sealed by a concrete decking and by concrete hatch covers. Seawater may be vented into the cells for cooling, through an integral vent arrangement. The vent ducts may be attached to pumps when the barge is bouyant. The ducts are also arranged to promote passive ventilation of the cells when the barge is submerged. Packages of the radwaste are loaded into individual cells within the barge. The cells are then sealed and the barge is towed to the designated disposal-storage site. There, the individual cells are flooded and the barge will begin descent controlled by a powered submarine control device to the seabed storage site. The submerged barge will rest on the seabed permanently or until recovered by a submarine control device.

Goldsberry, Fred L. (Spring, TX); Cawley, William E. (Richland, WA)

1981-01-01T23:59:59.000Z

82

Header Information  

National Nuclear Security Administration (NNSA)

26f27f Project Number Project 26g27g Material Type MaterialType 26h27h CompFacility Code CompCode IAEACompCode FacilityCompCode 26i27i Owner Code OwnerCode 26j27j Key...

83

Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk  

Science Conference Proceedings (OSTI)

In September 1996, the US Department of Energy, Richland Operations Office (RL) initiated the first of a two-phase program to remediate waste storage in tanks at the Hanford Site in Washington State. Initiating the first phase, RL signed contracts with two private companies who agreed to receive and vitrify a portion of the tank waste in a demonstration and to return the vitrified product and by-products to the Project Management Hanford Contract (PHMC) team for disposition. The first phase of the overall remediation effort is a demonstration of treatment concepts, and the second phase includes treatment of the remaining tank wastes. The demonstration phase, Phase 1 of the project, is further subdivided into two parts, A and B. During Phase 1A, the vitrification contractors are to establish the technical, operational, regulatory, business, and financial elements required to provide treatment services on a fixed unit price basis. Phase 1A deliverables will be evaluated by RL to determine whether it is in the best interest of the government to have one or more vitrification contractors proceed with Phase 1B, in which 6% to 13% of the tank waste would be treated in the demonstration. In addition, before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractor(s) and to receive and dispose of the products and by-products returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Project. Three RL core teams were established to assist in evaluating the PHMC team`s readiness specifically in regard to three task areas: Waste feed delivery; Infrastructure and by-products delivery; and Immobilized products. The core teams each developed a set of criteria and plans to be used in evaluating the PHMC team`s readiness to proceed (RTP).

Hall, C.E.

1998-01-06T23:59:59.000Z

84

Flare system for safe disposal of LNG from a disabled tanker  

SciTech Connect

The feasibility of a flare system for the rapid and safe incineration of the cargo of a disabled LNG tanker is evaluated. The project developed design parameters and proof-of-principle investigations of a system for off-loading and flaring LNG from a disabled LNG tanker. The system described offers enough promise to warrant additional investigation, if cargo burning is desired as a way of reducing other possible hazards.

Not Available

1982-12-01T23:59:59.000Z

85

PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED I. Test Results T-641317. Section 1. First issue, June 14, 1961  

SciTech Connect

Tests were performed to determine the adequacy of storage facilities and operating procedures of the Shippingport PWR waste disposal system during a reactor refueling operation. Problems associated with the liquid waste evaporator and the various storage tanks were outlined. The activities of the wastes expelled to the reactor effluent channel and the Ohio River were compared with the design activities. (T.F.H.)

1961-10-31T23:59:59.000Z

86

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success...

87

Predicting the fidelity of JPEG2000 compressed CT images using DICOM header information  

Science Conference Proceedings (OSTI)

Purpose: To propose multiple logistic regression (MLR) and artificial neural network (ANN) models constructed using digital imaging and communications in medicine (DICOM) header information in predicting the fidelity of Joint Photographic Experts Group (JPEG) 2000 compressed abdomen computed tomography (CT) images. Methods: Our institutional review board approved this study and waived informed patient consent. Using a JPEG2000 algorithm, 360 abdomen CT images were compressed reversibly (n = 48, as negative control) or irreversibly (n = 312) to one of different compression ratios (CRs) ranging from 4:1 to 10:1. Five radiologists independently determined whether the original and compressed images were distinguishable or indistinguishable. The 312 irreversibly compressed images were divided randomly into training (n = 156) and testing (n = 156) sets. The MLR and ANN models were constructed regarding the DICOM header information as independent variables and the pooled radiologists' responses as dependent variable. As independent variables, we selected the CR (DICOM tag number: 0028, 2112), effective tube current-time product (0018, 9332), section thickness (0018, 0050), and field of view (0018, 0090) among the DICOM tags. Using the training set, an optimal subset of independent variables was determined by backward stepwise selection in a four-fold cross-validation scheme. The MLR and ANN models were constructed with the determined independent variables using the training set. The models were then evaluated on the testing set by using receiver-operating-characteristic (ROC) analysis regarding the radiologists' pooled responses as the reference standard and by measuring Spearman rank correlation between the model prediction and the number of radiologists who rated the two images as distinguishable. Results: The CR and section thickness were determined as the optimal independent variables. The areas under the ROC curve for the MLR and ANN predictions were 0.91 (95% CI; 0.86, 0.95) and 0.92 (0.87, 0.96), respectively. The correlation coefficients of the MLR and ANN predictions with the number of radiologists who responded as distinguishable were 0.76 (0.69, 0.82, p < 0.001) and 0.78 (0.71, 0.83, p < 0.001), respectively. Conclusions: The MLR and ANN models constructed using the DICOM header information offer promise in predicting the fidelity of JPEG2000 compressed abdomen CT images.

Kim, Kil Joong; Kim, Bohyoung; Lee, Hyunna; Choi, Hosik; Jeon, Jong-June; Ahn, Jeong-Hwan; Lee, Kyoung Ho [Department of Radiation Applied Life Science, Seoul National University College of Medicine, 28 Yongon-dong, Chongno-gu, Seoul, 110-744 (Korea, Republic of); School of Computer Science and Engineering, Seoul National University, 599 Kwanak-Ro, Kwanak-Gu, Seoul, 151-742 (Korea, Republic of); Department of Informational Statistics, Hoseo University, 165, Sechul-ri, Baebang-myeon, Asan-si, Chungcheongnam-do, 336-795 (Korea, Republic of); Department of Statistics, Seoul National University, 599 Kwanak-Ro, Kwanak-Gu, Seoul, 151-742 (Korea, Republic of); Korean Intellectual Property Office, Government Complex-Daejeon, 139 Seonsa-ro, Seo-gu, Daejeon, 302-701 (Korea, Republic of); Department of Radiology, Seoul National University Bundang Hospital, Seoul National University College of Medicine, Institute of Radiation Medicine, and Seoul National University Medical Research Center, 300 Gumi-dong, Bundang-gu, Seongnam-si, Gyeonggi-do, 463-707 (Korea, Republic of)

2011-12-15T23:59:59.000Z

88

Header Sheet Doc ID Z OAK RIDGE NATIONAL LABORATORY M. E. Murray  

Office of Legacy Management (LM)

Dames & Moore Dames & Moore Header Sheet Doc ID Z OAK RIDGE NATIONAL LABORATORY M. E. Murray MANAGED BY LOCKHEED MARTIN rNERGY RESEARCH CORPORATION PHONE: (423) 574-5838 FOR THE U.S. DEPARTMENT OF ENERGY FAX: (423) POST OFFICE Box 2 INTERNET: r'0 March 31, 1997 Mr. Andrew Meloy DuPont Environmental Remediation Services DuPont Chambers Works Route 130, Anti-Knocks Building G Deepwater, New Jersey 08023 Dear Mr. Meloy: Radiological Sampling Requirements for the B Ditch Remediation Project, DuPont Chamber Works Site, Deepwater, New Jersey During the week of March 10, staff members of the Oak Ridge National Laboratory, Life Sciences Division, made surface radiation measurcments along the B ditch from 6+00' to the 11+00' markers. These measurements were performed to better define the subsurface

89

slc_disposal.cdr  

NLE Websites -- All DOE Office Websites (Extended Search)

Disposal Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site at Salt Lake City, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Salt Lake City, Utah, Disposal Site ENERGY Office of Legacy Management U.S. DEPARTMENT OF Site Description and History Regulatory Setting The Salt Lake Disposal Site is located approximately 81 miles west of Salt Lake City and 2.5 miles south of Interstate 80 on the eastern edge of the Great Salt Lake Desert. The disposal cell is adjacent to Energy Solutions, Inc., a commercial low-level radioactive materials disposal site. The surrounding area is sparsely populated, and the nearest residences are at least 15 miles from the site. Vegetation in the area is sparse and typical of semiarid low shrubland. The disposal cell encapsulates about

90

HNPF LIQUID WASTE DISPOSAL COST STUDY  

SciTech Connect

The HNPF cost analysis for waste disposal was made on the basis of 10,000 gallons of laundry waste and 9,000 gallons of other plant waste per year. The costs are compared for storage at HNPF site for 10 yr, packaging and shipment to AEC barial ground, packaging and shipment for sea disposal, and disposal by licensed vendor. A graphical comparison is given for the yearly costs of disposal by licensed vendor and the evaporator system as a function of waste volume. Recommendations are included for the handling of the wastes expected from HNPF operations. (B.O.G.)

Piccot, A.R.

1959-11-01T23:59:59.000Z

91

ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT  

Science Conference Proceedings (OSTI)

The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

2012-04-25T23:59:59.000Z

92

Material Disposal Areas  

NLE Websites -- All DOE Office Websites (Extended Search)

Material Disposal Areas Material Disposal Areas Material Disposal Areas Material Disposal Areas, also known as MDAs, are sites where material was disposed of below the ground surface in excavated pits, trenches, or shafts. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Material Disposal Areas at LANL The following are descriptions and status updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf). MDA A MDA A is a Hazard Category 2 nuclear facility comprised of a 1.25-acre, fenced, and radiologically controlled area situated on the eastern end of Delta Prime Mesa. Delta Prime Mesa is bounded by Delta Prime Canyon to the north and Los Alamos Canyon to the south.

93

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE`s Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS.

Price, L. [Science Applications International Corp., Albuquerque, NM (United States)

1994-09-01T23:59:59.000Z

94

Material Disposal Areas  

NLE Websites -- All DOE Office Websites (Extended Search)

wastewater absorption beds that received effluent from the DP Site radioactive laundry facility from 1945 to 1963, two surface debris disposal sites, and a former septic...

95

NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria  

SciTech Connect

At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

None

1981-04-01T23:59:59.000Z

96

A Parametric Study of a Large Break in Reactor Inlet Header of CANDU6 Reactors Using RELAP5 Code  

SciTech Connect

A large break loss of coolant accident in a CANDU can lead to degraded fuel cooling in a large number of fuel channels due to the apparition of a prolonged flow stagnation period in the downstream core pass. The paper presents a parametric study of a reactor inlet header break. The parametric survey includes: the size of the break, the choked flow model employed, the emergency core cooling (ECC) performance and the core nodalization. The study is performed with RELAP5/SCDAP mod 3.4 and the results are compared with the safety analysis results. (authors)

Prisecaru, Ilie; Dupleac, Daniel; Ghitescu, Petre [Power Plant Engineering Faculty, Politehnica Univ., 313 Splaiul Independentei, Bucharest (Romania); Biro, Lucian [National Commission for Nuclear Activities Control, 14 Libertatii Blvd., Bucharest (Romania)

2006-07-01T23:59:59.000Z

97

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Poultry Farm Daily Disposal Methods 0;Disposal: Science and Theory First Composter in Delaware ¬∑ Delmarva was of the first daily composting ¬∑ 120 in USA over next 10 years #12;Disposal: Science and Theory Composting Procedure ¬∑ Mixture ¬≠ 1 ¬Ĺ to 2

Benson, Eric R.

98

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Table of Contents · Disposal options emergency mortality composting procedure · Use of composting during outbreaks #12;Disposal: Science and disinfection of farms and surveillance around affected flocks. " USDA APHIS VS EMD, 2007 #12;Disposal: Science

Benson, Eric R.

99

Assessment of the impacts of spent fuel disassembly alternatives on the Nuclear Waste Isolation System. [Preparing and packaging spent fuel assemblies for geologic disposal  

SciTech Connect

The objective of this report was to evaluate four possible alternative methods of preparing and packaging spent fuel assemblies for geologic disposal against the Reference Process of unmodified spent fuel. The four alternative processes were: (1) End fitting removal, (2) Fission gas venting and resealing, (3) Fuel bundle disassembly and close packing of fuel pins, and (4) Fuel shearing and immobilization. Systems analysis was used to develop a basis of comparison of the alternatives. Conceptual processes and facility layouts were devised for each of the alternatives, based on technology deemed feasible for the purpose. Assessments were made of 15 principal attributes from the technical, operational, safety/risk, and economic considerations related to each of the alternatives, including both the surface packaging and underground repository operations. Specific attributes of the alternative processes were evaluated by assigning a number for each that expressed its merit relative to the corresponding attribute of the Reference Process. Each alternative process was then ranked by summing the numbers for attributes in each of the four assessment areas and collectively. Fuel bundle disassembly and close packing of fuel pins was ranked the preferred method of disposal of spent fuel. 63 references, 46 figures, 46 tables.

Not Available

1984-07-01T23:59:59.000Z

100

Cost of meeting geothermal liquid effluent disposal regulations  

DOE Green Energy (OSTI)

Background information is presented on the characteristics of liquid wastes and the available disposal options. Regulations that may directly or indirectly influence liquid waste disposal are reviewed. An assessment of the available wastewater-treatment systems is provided. A case study of expected liquid-waste-treatment and disposal costs is summarized. (MHR)

Wells, K.D.; Currie, J.W.; Price, B.A.; Rogers, E.A.

1981-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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101

Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms  

SciTech Connect

This report provides a technical assessment of the Melt-Dilute and Direct Al-SNF forms in disposable canisters with respect to meeting the requirements for disposal in the Mined Geologic Disposal System (MGDS) and for interim dry storage in the Treatment and Storage Facility (TSF) at SRS.

Vinson, D.W.

1998-11-06T23:59:59.000Z

102

Delicate disposal of PCBs  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) has published three handbooks to help utilities evaluate the alternatives for disposal of polychlorinated biphenyls (PCBs), which will continue to be a utility responsibility for some time. The identification of PCBs as a toxic substance in 1976 ended their use as a capacitor and transformer insulator, but 375 million pounds are distributed in equipment and their disposal must be carefully planned. The booklets outline Environmental Protection Agency (EPA) regulations, the disposal technology by incineration or landfill which is currently available, and guidelines for preventing spills and controlling risks. (DCK)

Lihach, N.; Golden, D.

1980-03-01T23:59:59.000Z

103

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

request for further delays After the EPA certified that the WIPP met the standards for disposal of transuranic waste in May 1998, then-New Mexico Attorney General Tom Udall...

104

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

Department of Energy (DOE) is closing the circle on the generation, management, and disposal of transuranic waste. But the WIPP story is not just about radioactive waste. It is...

105

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Use of Composting · Composting has ­ British Columbia 2009 #12;Disposal: Science and Theory · Initial farm linked to NY LBM · Two additional and pile procedure Delmarva 2004 #12;Disposal: Science and Theory Delmarva 2004 · Composting used

Benson, Eric R.

106

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foam Used in Actual Outbreak · Water #12;Disposal: Science and Theory Water Based Foam Culling Demo · First large scale comparison · Two:46 (m:s) #12;Disposal: Science and Theory WV H5N2 AIV 2007 · AIV positive turkeys ­ 25,000 turkey farm

Benson, Eric R.

107

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · El compostaje se ha usado como Virginia (2007) ­ British Columbia (2009) Uso del compostaje #12;Disposal: Science and Theory · Primera apilamiento Delmarva (2004) #12;Disposal: Science and Theory · El compostaje se usó para proteger una densa

Benson, Eric R.

108

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Compostaje de aves de corralRouchey et al., 2005) Investigación previa #12;Disposal: Science and Theory · Se ha evaluado y documentado el, bovino Investigación previa #12;Disposal: Science and Theory · Experimento nro. 1 Impacto de la espuma en

Benson, Eric R.

109

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory ¬∑ Opciones para la eliminaci√≥n ¬∑ ¬ŅQu√© compostaje durante brotes de enfermedades Lista de contenido #12;Disposal: Science and Theory "Ante un brote brotes de IIAP #12;Disposal: Science and Theory ¬∑ En 2004, se despoblaron 100 millones de aves en todo el

Benson, Eric R.

110

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory ¬∑ Las recomendaciones de campo se la espuma #12;Disposal: Science and Theory ¬∑ M√ļltiples especies de aves pueden despoblarse con espuma cesaci√≥n #12;Disposal: Science and Theory ¬∑ Dentro de una especie, pueden existir variaciones ¬≠ Los √°nades

Benson, Eric R.

111

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Opciones para la producción de espuma espuma · Sistemas de boquilla #12;Disposal: Science and Theory Requisitos estimados: · Tiempo: 2 a 3 compactas ­ Equipo de respuesta propio de la industria Espuma de aire comprimido #12;Disposal: Science

Benson, Eric R.

112

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Summary · Foam is currently a viable ­ Foam application directly to cage #12;Disposal: Science and Theory Legal Status of Foam · Procedure depopulation, culling, and euthanasia #12;Disposal: Science and Theory Acknowledgements · USDA AICAP2 · USDA

Benson, Eric R.

113

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Mass Emergency Composting · Basic ­ Create carcass and litter windrow #12;Disposal: Science and Theory Mass Emergency Composting · Basic cover ­ Clean and disinfect house ­ Sample for virus again #12;Disposal: Science and Theory Mass

Benson, Eric R.

114

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Gassing is a preferred #12;Disposal: Science and Theory Carbon Dioxide Gassing · Carbon dioxide (CO2) one of the standard sensitivity time #12;Disposal: Science and Theory · Argon-CO2 gas depopulation evaluated under laboratory

Benson, Eric R.

115

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foam Generator Setup · Drop off foam generator cart at one end of house #12;Disposal: Science and Theory Foam Generator Setup · Trailer parked generator attached to hose #12;Disposal: Science and Theory Foam Generation Begins · Team of two to operate

Benson, Eric R.

116

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory 2004 ¬≠ Participaci√≥n de Bud Malone y la espuma 2009 ¬≠ Ninguna ventaja para el gas Breve historia de la espuma #12;Disposal: Science sistema de boquilla ¬ŅQu√© es la espuma? #12;Disposal: Science and Theory ¬∑ La espuma puede incluir: ¬≠ Una

Benson, Eric R.

117

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory 0 20 40 60 80 100 Compostaje #12;Disposal: Science and Theory ¬∑ Delmarva fue de las primeras granjas en realizar el compostaje de en EE.UU. en los pr√≥ximos 10 a√Īos. Pionera en compostaje en Delaware #12;Disposal: Science and Theory

Benson, Eric R.

118

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Procedimiento básico ­ Desarrollar una pila de carcasas y lecho. Compostaje masivo de emergencia #12;Disposal: Science and Theory de emergencia #12;Disposal: Science and Theory · Desarrollar planes antes de que ocurra una

Benson, Eric R.

119

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Composting · Composting is defined drop #12;Disposal: Science and Theory Composting · Optimal composting ­ Carbon to nitrogen ratio (C;Disposal: Science and Theory Compost Composition · A variety of supplemental carbon materials have been

Benson, Eric R.

120

Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report  

SciTech Connect

Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases.

1979-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Integrated Used Nuclear Fuel Storage, Transportation, and Disposal ...  

ORNL 2011-G00239/jcn UUT-B ID 201102603 09.2011 Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Technology Summary

122

Sample storage/disposal study  

SciTech Connect

Radioactive waste from defense operations has accumulated at the Hanford Site`s underground waste tanks since the late 1940`s. Each tank must be analyzed to determine whether it presents any harm to the workers at the Hanford Site, the public or the environment. Analyses of the waste aids in the decision making process in preparation of future tank waste stabilization procedures. Characterization of the 177 waste tanks on the Hanford Site will produce a large amount of archived material. This also brings up concerns as to how the excess waste tank sample material from 325 and 222-S Analytical Laboratories will be handled. Methods to archive and/or dispose of the waste have been implemented into the 222-S and 325 Laboratory procedures. As the amount of waste characterized from laboratory analysis grows, an examination of whether the waste disposal system will be able to compensate for this increase in the amount of waste needs to be examined. Therefore, the need to find the safest, most economically sound method of waste storage/disposal is important.

Valenzuela, B.D.

1994-09-29T23:59:59.000Z

123

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Landfill Reaches 15 Million Tons Disposed - Waste Disposal Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor July 9, 2013 - 12:00pm Addthis Media Contacts Cameron Hardy, DOE, (509) 376-5365 Cameron.Hardy@rl.doe.gov Mark McKenna, WCH, (509) 372-9032 media@wch-rcc.com RICHLAND, Wash. - The U.S. Department of Energy (DOE) and its contractors have disposed of 15 million tons of contaminated material at the Environmental Restoration Disposal Facility (ERDF) since the facility began operations in 1996. Removing contaminated material and providing for its safe disposal prevents contaminants from reaching the groundwater and the Columbia River. ERDF receives contaminated soil, demolition debris, and solid waste from

124

disposal_cell.cdr  

Office of Legacy Management (LM)

With the With the April 24, 1997, ceremonial ground-breaking for disposal facility construction, the Weldon Spring Site Remedial Action Project (WSSRAP) moved into the final stage of cleanup, treatment, and disposal of uranium- processing wastes. The cleanup of the former uranium- refining plant consisted of three primary operations: Demolition and removal of remaining concrete pads and foundations that supported the 44 structures and buildings on site Treatment of selected wastes Permanent encapsulation of treated and untreated waste in an onsite engineered disposal facility In September l993, a Record of Decision (ROD) was signed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE), with concurrence by the Missouri Department of Natural

125

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOECAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of...

126

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

127

Waste disposal package  

DOE Patents (OSTI)

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

128

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Previous Research · Composting, et.al. 2005; Bendfeldt et al., 2006; DeRouchey et al., 2005) #12;Disposal: Science and Theory: Science and Theory Scientific Validation of Composting · Experiment 1 Impact of foam on composting

Benson, Eric R.

129

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Field recommendations based of activity ­ Corticosterone ­ EEG, ECG and motion studies · Large scale testing ­ Field scale units Science of Foam #12;Disposal: Science and Theory Cessation Time · Multiple bird species can be depopulated

Benson, Eric R.

130

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory ¬∑ Se ubica el carret√≥n con el enfriamiento Ventiladores de t√ļnel de viento #12;Disposal: Science and Theory ¬∑ Se estaciona el remolque en uno: Science and Theory ¬∑ Se usa un equipo de dos personas para hacer funcionar el sistema: ¬≠ Operario del

Benson, Eric R.

131

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · El compostaje se define como la: Science and Theory · Compostaje óptimo ­ Relación carbono/nitrógeno (C:N): 20:1 a 35:1 ­ Contenido de Compostaje #12;Disposal: Science and Theory · Se ha utilizado satisfactoriamente una variedad de materiales

Benson, Eric R.

132

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Table of Contents · Why Depopulate? · Depopulation Methods · Basics of Foam · Types of Foam Equipment · Science Behind Foam · Implementing Foam Depopulation · Use of Foam in the Field · Conclusions #12;Disposal: Science and Theory "When HPAI outbreaks

Benson, Eric R.

133

High-R Walls for New Construction Structural Performance: Integrated Rim Header Testing  

Science Conference Proceedings (OSTI)

Two prominent approaches within the Building America Program to construct higher R-value walls have included use of larger dimension framing and exterior rigid foam insulation. These approaches have been met with some success; however for many production builders, where the cost of changing framing systems is expensive, the changes have been slow to be realized. In addition, recent building code changes have raised some performance issues for exterior sheathing and raised heel trusses, for example, that indicates a need for continued performance testing for wall systems.

DeRenzis, A.; Kochkin, V.; Wiehagen, J.

2013-01-01T23:59:59.000Z

134

Dredged and Fill Material Disposal (North Dakota) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dredged and Fill Material Disposal (North Dakota) Dredged and Fill Material Disposal (North Dakota) Dredged and Fill Material Disposal (North Dakota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State North Dakota Program Type Siting and Permitting This chapter provides regulations for the disposal of dredged and fill

135

Chapter 37 Land Disposal Restrictions (Kentucky) | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7 Land Disposal Restrictions (Kentucky) Chapter 37 Land Disposal Restrictions (Kentucky) Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor...

136

Waste Disposal (Illinois) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Disposal (Illinois) Waste Disposal (Illinois) Eligibility Commercial Construction Industrial Utility Program Information Illinois Program Type Environmental Regulations This...

137

ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS...  

NLE Websites -- All DOE Office Websites (Extended Search)

DISPOSAL RECORDS (Revision 2) More Documents & Publications Records Management Handbook PROPERTY DISPOSAL RECORDS ADMINISTRATIVE RECORDS SCHEDULE 9: TRAVEL AND...

138

Mapping of a reactor coolant effluent ground disposal test using an infrared imaging system and ground water potential and temperature measurements  

SciTech Connect

The concept of reactor effluent disposal to ground in infiltration trenches was proposed by Nelson and Alkire in 1963. At that time the available data indicated that radionuclide infiltration rates were probably adequate for trench disposal and that decontamination factors of 10 to 100 should be obtainable. Field tests at 100-F Area 1965 and 100-D Area 1967 have indicated that the infiltration rates are adequate and DF`s of from 2.5 for {sup 51}Cr to 7276 for {sup 65}Zn were obtained during the 100-D test. The purpose of this report is to present the results and interpretations of data from studies conducted over a reactor coolant effluent disposal test site. Data presented in this report were collected over the 100-C Area test in which a significant percentage of the reactor coolant effluent was disposed to an existing trench for a five-month period. Results of infrared thermal surveys and ground water temperature and potential measurements collected during this test are presented.

Eliason, J.R.

1969-04-10T23:59:59.000Z

139

FGD By-Product Disposal Manual, Fourth Edition  

Science Conference Proceedings (OSTI)

This manual presents an objective, systematic methodology for evaluating potential flue gas desulfurization (FGD) sludge disposal sites and design approaches. A completely updated edition, the manual provides new information and references on existing industry disposal practices, regulatory constraints and trends, FGD sludge properties, and waste management system costs.

1995-08-11T23:59:59.000Z

140

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

142

WEB RESOURCE: Nuclear Waste Disposal  

Science Conference Proceedings (OSTI)

May 10, 2007 ... The complete "Yucca Mountain Resource Book" is also available for download at this site. Citation: Nuclear Waste Disposal. 2007. Nuclear†...

143

Waste disposal and renewable resources.  

E-Print Network (OSTI)

?? Purpose/aim: The purpose of this dissertation is to find out the effect of waste disposal on environment and to explore the effect of renewableÖ (more)

Hai, Qu; PiaoYi, Sun

2013-01-01T23:59:59.000Z

144

Continuing disposal of coal ash  

Science Conference Proceedings (OSTI)

The large volume of power-plant coal ash produced and stricter Federal water pollution controls are making ash disposal increasingly difficult for utilities. The protection of surface and ground water quality required in the Resource conservation and Recovery Act of 1976 (RCRA) and the Federal Water Pollution Control Act's Clean Water Act (CWA) amendments of 1977 have raised the cost of disposal to a level where an acceptable method must be found. The Electric Power Research Institute's Coal Ash Disposal Manual (EPRI-FM--1257) describes-ash chemistry, disposal site selection, site monitoring and reclamation, and other information of interest to utilities that are making cost estimates and procedure evaluations. (DCK)

Lihach, N.; Golden, D.

1980-03-01T23:59:59.000Z

145

Treatment and Disposal of Unanticipated 'Scavenger' Wastewater  

Science Conference Proceedings (OSTI)

The Savannah River Site often generates wastewater for disposal that is not included as a source to one of the site's wastewater treatment facilities that are permitted by the South Carolina Department of Health and Environmental Control. The techniques used by the SRS contract operator (Westinghouse Savannah River Company) to evaluate and treat this unanticipated 'scavenger' wastewater may benefit industries and municipalities who experience similar needs. Regulations require that scavenger wastewater be treated and not just diluted. Each of the pollutants that are present must meet effluent permit limitations and/or receiving stream water quality standards. if a scavenger wastewater is classified as 'hazardous' under the Resource Conservation and Recovery Act (RCRA) its disposal must comply with RCRA regulations. Westinghouse Savannah River Company obtained approval from SCDHEC to dispose of scavenger wastewater under specific conditions that are included within the SRS National Pollutant Discharge Elimination System permit. Scavenger wastewater is analyzed in a laboratory to determine its constituency. Pollutant values are entered into spreadsheets that calculate treatment plant removal capabilities and instream concentrations. Disposal rates are computed, ensuring compliance with regulatory requirements and protection of treatment system operating units. Appropriate records are maintained in the event of an audit.

Payne, W.L.

2003-09-15T23:59:59.000Z

146

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

147

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

148

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

44060 PI: Dr. Adel Mansour (e-mail: amansour@parker.com, Ph.: 440-954-8171) University of California at Irvine UCI Combustion Laboratory, Irvine, CA 92617 Solar Turbines...

149

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

instrumented to measure performance and operational characteristics of the test rotor. A parallel effort constructed analytical performance prediction tools and the...

150

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

AL05205018 - Analysis of Gas Turbine Thermal Performance FACT SHEET I. PROJECT PARTICIPANTS Ames National Laboratory Oak Ridge National Laboratory (funded separately) II. PROJECT...

151

Header with Project Title  

NLE Websites -- All DOE Office Websites (Extended Search)

this project is to design and develop a fuel flexible (coal derived hydrogen or syngas) gas turbine for IGCC and FutureGen type applications that meets DOE turbine performance...

152

Chemistry of glass-ceramic to metal bonding for header applications. I. Effect of treatments on Inconel 718 and Hastelloy C-276 metallic surfaces  

SciTech Connect

Auger electron spectroscopy and depth Auger profiling were used to study the surfaces of Inconel 718 and Hastelloy C-276. The metal surfaces were processed in the same manner as is presently being used in the manufacturing of glass-ceramic headers. At each step in the process, samples were studied with Auger spectroscopy to determine their resultant elemental surface composition and film thickness. In addition, the effect of a final plasma cleaning operation on the metal surface was examined. The results show that the type and concentration of surface species and the thickness of the surface oxides are dependent on the processing technique.

Kramer, D P; Craven, S M; Schneider, R E; Moddeman, W E; Brohard, D W

1984-02-02T23:59:59.000Z

153

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network (OSTI)

2/07 WASTE DISPOSAL SECTION CORNELL UNIVERSITY PROCEDURE for DISPOSAL of RADIOACTIVE MATERIALS This procedure has been developed to ensure the safety of those individuals who handle radioactive waste identified hazardous waste, or other unusual issues require special consideration. Contact the Department

Manning, Sturt

154

Autonomous grain combine control system  

DOE Patents (OSTI)

A system for controlling a grain combine having a rotor/cylinder, a sieve, a fan, a concave, a feeder, a header, an engine, and a control system. The feeder of the grain combine is engaged and the header is lowered. A separator loss target, engine load target, and a sieve loss target are selected. Grain is harvested with the lowered header passing the grain through the engaged feeder. Separator loss, sieve loss, engine load and ground speed of the grain combine are continuously monitored during the harvesting. If the monitored separator loss exceeds the selected separator loss target, the speed of the rotor/cylinder, the concave setting, the engine load target, or a combination thereof is adjusted. If the monitored sieve loss exceeds the selected sieve loss target, the speed of the fan, the size of the sieve openings, or the engine load target is adjusted.

Hoskinson, Reed L.; Kenney, Kevin L.; Lucas, James R.; Prickel, Marvin A.

2013-06-25T23:59:59.000Z

155

Research, Development, and Demonstration Roadmap for Deep Borehole Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Research, Development, and Demonstration Roadmap for Deep Borehole Research, Development, and Demonstration Roadmap for Deep Borehole Disposal Research, Development, and Demonstration Roadmap for Deep Borehole Disposal This roadmap is intended to advance deep borehole disposal (DBD) from its current conceptual status to potential future deployment as a disposal system for spent nuclear fuel (SNF) and high-level waste (HLW). The objectives of the DBD RD&D roadmap include providing the technical basis for fielding a DBD demonstration project, defining the scientific research activities associated with site characterization and postclosure safety, as well as defining the engineering demonstration activities associated with deep borehole drilling, completion, and surrogate waste canister emplacement. Research, Development, and Demonstration Roadmap for Deep Borehole Disposal

156

Low level tank waste disposal study  

SciTech Connect

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

Mullally, J.A.

1994-09-29T23:59:59.000Z

157

UNREVIEWED DISPOSAL QUESTION EVALUATION: WASTE DISPOSAL IN ENGINEERED TRENCH #3  

SciTech Connect

Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Hamm, L.; Smith, F.; Flach, G.; Hiergesell, R.; Butcher, T.

2013-07-29T23:59:59.000Z

158

Health Risks Associated with Disposal of Depleted Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

Disposal DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Disposal of Depleted Uranium A discussion of risks associated with disposal...

159

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

Science Conference Proceedings (OSTI)

The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.

Esh, David W.; Bradford, Anna H. [U.S. Nuclear Regulatory Commission, Two White Flint North, MS T7J8, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2008-01-15T23:59:59.000Z

160

Documents: Disposal of DUF6 Conversion Products  

NLE Websites -- All DOE Office Websites (Extended Search)

DUF6 Conversion Products Search Documents: Search PDF Documents View a list of all documents Disposal of DUF6 Conversion Products PDF Icon Engineering Analysis for Disposal of...

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Environmental Risks of Depleted UF6 Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Disposal A discussion of the environmental impacts...

162

Assessment of Preferred Depleted Uranium Disposal Forms  

NLE Websites -- All DOE Office Websites (Extended Search)

. . 7 3.2 PRELIMINARY ASSESSMENT OF DU DISPOSAL AT OTHER SITES . . . . . . . . . . 8 3.3 COSTS OF PRODUCTION, TRANSPORTATION, AND DISPOSAL OF DU WASTE FORMS . . . . . . . . . . ....

163

PROPERTY DISPOSAL RECORDS | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

DISPOSAL RECORDS More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) Records Management Handbook Inspection Report: INS-O-02-01...

164

Demilitarization and disposal technologies for conventional munitions and energetic materials  

SciTech Connect

Technologies for the demilitarization and disposal of conventional munitions and energetic materials are presented. A hazard separation system has been developed to remove hazardous subcomponents before processing. Electronic component materials separation processes have been developed that provide for demilitarization as well as the efficient recycling of materials. Energetic materials demilitarization and disposal using plasma arc and molten metal technologies are currently being investigated. These regulatory compliant technologies will allow the recycling of materials and will also provide a waste form suitable for final disposal.

Lemieux, A.A.; Wheelis, W.T.; Blankenship, D.M.

1994-09-01T23:59:59.000Z

165

WIPP - Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Disposal Cover Page and Table of Contents Closing the Circle The Long Road to WIPP - Part 1 The Long Road to WIPP - Part 2 Looking to the Future Related Reading and The...

166

Solid Waste Disposal Act (Texas)  

Energy.gov (U.S. Department of Energy (DOE))

The Texas Commission on Environmental Quality is responsible for the regulation and management of municipal solid waste and hazardous waste. A fee is applied to all solid waste disposed in the...

167

Scenarios of the TWRS low-level waste disposal program  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 Area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pretreating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1994-10-01T23:59:59.000Z

168

Tank Waste Disposal Program redefinition  

SciTech Connect

The record of decision (ROD) (DOE 1988) on the Final Environmental Impact Statement, Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland Washington identifies the method for disposal of double-shell tank waste and cesium and strontium capsules at the Hanford Site. The ROD also identifies the need for additional evaluations before a final decision is made on the disposal of single-shell tank waste. This document presents the results of systematic evaluation of the present technical circumstances, alternatives, and regulatory requirements in light of the values of the leaders and constitutents of the program. It recommends a three-phased approach for disposing of tank wastes. This approach allows mature technologies to be applied to the treatment of well-understood waste forms in the near term, while providing time for the development and deployment of successively more advanced pretreatment technologies. The advanced technologies will accelerate disposal by reducing the volume of waste to be vitrified. This document also recommends integration of the double-and single-shell tank waste disposal programs, provides a target schedule for implementation of the selected approach, and describes the essential elements of a program to be baselined in 1992.

Grygiel, M.L.; Augustine, C.A.; Cahill, M.A.; Garfield, J.S.; Johnson, M.E.; Kupfer, M.J.; Meyer, G.A.; Roecker, J.H. [Westinghouse Hanford Co., Richland, WA (United States); Holton, L.K.; Hunter, V.L.; Triplett, M.B. [Pacific Northwest Lab., Richland, WA (United States)

1991-10-01T23:59:59.000Z

169

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

170

Low and medium level radioactive waste disposal in France  

Science Conference Proceedings (OSTI)

ANDRA, as the national radioactive waste management agency of France, was created in 1979 as part of the French Atomic Energy, Commission and is responsible for radioactive waste disposal. Legislation passed on December 30, 1991 gave ANDRA greater autonomy and responsibility for radioactive waste management by making it a Public Service Company separate from the CEA and by placing it under the supervisory authority of the Ministries of Industry, of the Environment and of Research. The legislation specifically delegates the following responsibilities to ANDRA: (1) establishment of specifications for radioactive waste solidification and disposal; (2) design, siting and construction of new waste disposal facilities; (3) disposal facility operations; and (4) participation in research on, and design and construction of, isolation systems for long lived waste.

Potier, J.M.

1994-12-31T23:59:59.000Z

171

Depleted uranium disposal options evaluation  

SciTech Connect

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

1994-05-01T23:59:59.000Z

172

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

173

Strategy for the Management and Disposal of Used Nuclear Fuel and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Issued on January 11, 2013, the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High Level Radioactive Waste.pdf More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and

174

Strategy for the Management and Disposal of Used Nuclear Fuel and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste The Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste

175

Electrochemical Apparatus with Disposable and Modifiable Parts  

NLE Websites -- All DOE Office Websites (Extended Search)

Electrochemical Apparatus with Disposable and Modifiable Parts Electrochemical Apparatus with Disposable and Modifiable Parts Electrochemical Apparatus with Disposable and Modifiable Parts The invention also includes electrochemical apparatus that can interface with optical instrumentation. If the working electrode is transparent, light from an optical fiber may be directed through the working electrode and into a cuvette. July 3, 2013 Electrochemical Apparatus with Disposable and Modifiable Parts Available for thumbnail of Feynman Center (505) 665-9090 Email Electrochemical Apparatus with Disposable and Modifiable Parts Applications: Electrochemical experiments in solution Electrochemical experiments on surfaces Bulk electrolysis experiments Fuel cells Corrosion studies Academic Labs Teaching and research Benefits: Incorporates disposable, commercially available cuvettes

176

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network (OSTI)

Laboratory Waste Disposal HAZARDOUS GLASS Items that could cut or puncture skin or trash- can liners. This waste stream must be boxed to protect custodial staff. It goes directly to the landfill lined cardboard box. Tape seams with heavy duty tape to contain waste. Limit weight to 20 lbs. Or

Sheridan, Jennifer

177

Manage fuel gas with an expert system  

Science Conference Proceedings (OSTI)

The Star Louisiana refinery has fuel gas header systems throughout the plant that are utilized by fuel gas producers and consumers. The refinery simultaneously exports surplus fuel gas from the export gas header, and maintains a minimum natural gas makeup rates from multiple external suppliers for fuel gas header pressure control. Successfully implementing a fuel gas expert system has facilitated communication of accurate, timely information to all unit control board operators in the refinery when any change or sub-optimal situation occurs in either of these systems. Information provided from the expert system rule knowledge base results in: proper unit operating actions taken when a flaring situation approaches, thus minimizing the negative impact of flaring on the environment and minimizing product loses to the flare; minimizing purchase of makeup natural gas used for fuel gas system pressure control; maximizing export gas capacity to prevent surplus fuel gas production from limiting refinery operation; immediately recognizing an upset in any fuel gas header system and advising the best corrective action for all affected refinery units; and minimizing voice communication required between units in an upset, since the expert system provides the communication immediately in expert advice messages.

Giacone, G.; Toben, S.; Bergeron, G. [Star Enterprise, Convent, LA (United States); Ayral, T. [Key Control Inc., Westlake Village, CA (United States)

1996-09-01T23:59:59.000Z

178

Acceptance test procedure: RMW Land Disposal Facility Project W-025  

SciTech Connect

This ATP establishes field testing procedures to demonstrate that the electrical/instrumentation system functions as intended by design for the Radioactive Mixed Waste Land Disposal Facility. Procedures are outlined for the field testing of the following: electrical heat trace system; transducers and meter/controllers; pumps; leachate storage tank; and building power and lighting.

Roscha, V. [Westinghouse Hanford Co., Richland, WA (United States)

1994-12-12T23:59:59.000Z

179

DISPOSAL OF RADIOACTIVE WASTE ON LAND  

SciTech Connect

Two years' consideration of the disposal problem by the National Research Council Committee on Waste Disposal has led to certain conclusions which are presented. Waste may be safely disposed of at many sites in the United States but conversely there are many large areas in which it is unlikely that disposal sites can be found as, for example, the Atlantic seaboard. The research to ascertain feasibility of disposal hss for the most part not yet been done. The most practical immediate solution of the problem suggests disposal in cavities mined in salt beds or domes. Disposal could be greatly simplified if the waste could be gotten into solid form of relatively insoluble character. Disposal in porous beds underground has capabilities of taking large volumes but will require considerable research to mske the waste compatible with such an environment. The main difficulty with this method at present is to prevent clogging of pore space as waste is pumped in. (auth)

Hess, H.H.; Thurston, W.R.

1958-06-01T23:59:59.000Z

180

Disposal of NORM waste in salt caverns  

Science Conference Proceedings (OSTI)

Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

1998-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Changes in Vegetation at the Monticello, Utah, Disposal Site...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal...

182

Disposal Practices at the Nevada Test Site 2008 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at...

183

FAQ 42-What are the potential environmental impacts from disposal...  

NLE Websites -- All DOE Office Websites (Extended Search)

disposal of depleted uranium as an oxide? What are the potential environmental impacts from disposal of depleted uranium as an oxide? Disposal as oxide could result in adverse...

184

Repository Reference Disposal Concepts and Thermal Load Management...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists...

185

CX-010401: Categorical Exclusion Determination  

Energy.gov (U.S. Department of Energy (DOE))

Replace Brine Disposal System Header to West Hackberry Brine Tanks CX(s) Applied: B1.3 Date: 04/22/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

186

Waste disposal options report. Volume 1  

SciTech Connect

This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01T23:59:59.000Z

187

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL #12;#12;PNNL-SA-69994 Waste Disposal Workshops: Anthrax- Contaminated Waste AM Lesperance JF Upton SL

188

Decontamination of Reactor Systems and Contaminated Components for Disposal or Refurbishment: Developments and Experience with the EPRI DFD Chemical Decontamination Process  

Science Conference Proceedings (OSTI)

This report describes recent developments using the EPRI (Decontamination for Decommissioning (DFD) dilute chemical decontamination process on reactor coolant systems and components. The nuclear industry has now used the process for a variety of applications, from cleaning small components to full system decontamination of retired plants. The report documents substantial savings in radiation exposures during decommissioning work and discusses the benefits of using the process to reduce radioactive waste ...

2001-11-05T23:59:59.000Z

189

REGULATIONS ON PHOTOVOLTAIC MODULE DISPOSAL AND RECYCLING.  

Science Conference Proceedings (OSTI)

Environmental regulations can have a significant impact on product use, disposal, and recycling. This report summarizes the basic aspects of current federal, state and international regulations which apply to end-of-life photovoltaic (PV) modules and PV manufacturing scrap destined for disposal or recycling. It also discusses proposed regulations for electronics that may set the ground of what is to be expected in this area in the near future. In the US, several states have started programs to support the recycling of electronic equipment, and materials destined for recycling often are excepted from solid waste regulations during the collection, transfer, storage and processing stages. California regulations are described separately because they are different from those of most other states. International agreements on the movement of waste between different countries may pose barriers to cross-border shipments. Currently waste moves freely among country members of the Organization of Economic Cooperation and Development (OECD), and between the US and the four countries with which the US has bilateral agreements. However, it is expected, that the US will adopt the rules of the Basel Convention (an agreement which currently applies to 128 countries but not the US) and that the Convection's waste classification system will influence the current OECD waste-handling system. Some countries adopting the Basel Convention consider end-of-life electronics to be hazardous waste, whereas the OECD countries consider them to be non-hazardous. Also, waste management regulations potentially affecting electronics in Germany and Japan are mentioned in this report.

FTHENAKIS,V.

2001-01-29T23:59:59.000Z

190

Environmental waste disposal contracts awarded  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

191

Development of the EPRI DFDX Chemical Decontamination Process: A New Process for the Chemical Decontamination of Nuclear Systems and Components for Disposal or Refurbishment  

Science Conference Proceedings (OSTI)

This report describes the development of the EPRI DFDX process for the chemical decontamination of reactor coolant systems and components. This new process is an enhancement of the EPRI DFD process, which utility operators have used widely for decontamination of retired reactors and plant components. The process uses electrochemical ion exchange technology, which reduces the volume of secondary radioactive waste by a factor of up to 10. The project team has completed development, filed a patent applicati...

2002-09-26T23:59:59.000Z

192

Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)  

SciTech Connect

This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.

Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.

1986-06-01T23:59:59.000Z

193

RADIOACTIVE WASTE DISPOSAL AT KNOLLS ATOMIC POWER LABORATORY  

SciTech Connect

One of Its Monograph Series The Industrial Atom.'' Disposal of radioactive wastes from KAPL is considered with respect to the three physical categories of waste--solid, liquid, and airborne---and the three environmental recipients ---ground, surface water, and atmosphere. Solid waste-handling includes monitoring radiation levels, segregation, collection, processing, packaging, storing if necessary, and shipping to a remote burial ground at the Oak Ridge National Laboratory. Liquid waste is collected by controlled drain systems, monitored for radioactivity content, and stored if necessary or released to the Mohawk River. Exhaust air is cleaned before released and con tinuously monitored. rhe environment is monitored to assure safe and proper disposal of wastes. The cost of operations and the depreciation of facilities incurred by KAPL for disposing of radioactive contaminated waste is less than 0.7% per year of the tofal cost of the Laboratory. (auth)

Manieri, D.A.; Truran, W.H.

1958-03-01T23:59:59.000Z

194

Idaho CERCLA Disposal Facility at Idaho National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Operations Idaho Operations Review of the Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory By Craig H. Benson, PhD, PE; William H. Albright, PhD; David P. Ray, PE, and John Smegal Sponsored by: The Office of Engineering and Technology (EM-20) 5 December 2007 i TABLE OF CONTENTS 1. INTRODUCTION 1 2. OBJECTIVE AND SCOPE 1 3. LINE OF INQUIRY NO. 1 2 3.1 Containerized Waste 2 3.2 Compacted Mixtures of Soil and Debris 3 3.3 Final Cover Settlement 3 3.4 Leachate Collection System and Leak Detection Zone Monitoring 4 4. LINE OF INQUIRY NO. 2 4 5. LINE OF INQUIRY NO. 3 5 6. SUMMARY OF RECOMMENDATIONS 6 7. ACKNOWLEDGEMENTS 6 FIGURES 7 1 1. INTRODUCTION The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility authorized by the US

195

Ultimate Disposal of Wastes by Pyrolysis and Incineration  

E-Print Network (OSTI)

fan into the stack to atmosphere. The system incorporates the latest available designs in combustion This paper describes a new disposal facility designed to reduce thermally, without causing pollution, liq authorized the design and construction of a facility to reduce liquid/fluid industrial wastes by pyrolysis

Columbia University

196

Readiness Assessment Plan, Hanford 200 areas treated effluent disposal facilities  

SciTech Connect

This Readiness Assessment Plan documents Liquid Effluent Facilities review process used to establish the scope of review, documentation requirements, performance assessment, and plant readiness to begin operation of the Treated Effluent Disposal system in accordance with DOE-RLID-5480.31, Startup and Restart of Facilities Operational Readiness Review and Readiness Assessments.

Ulmer, F.J.

1995-02-06T23:59:59.000Z

197

Comparison of low-level waste disposal programs of DOE and selected international countries  

SciTech Connect

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada`s first demonstration LLW disposal facility.

Meagher, B.G. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Cole, L.T. [Cole and Associates (United States)

1996-06-01T23:59:59.000Z

198

UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1  

SciTech Connect

This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system`s designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy.

NONE

1995-10-01T23:59:59.000Z

199

Aerosol can waste disposal device  

DOE Patents (OSTI)

Disclosed is a device for removing gases and liquid from containers. The ice punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container.

O' Brien, Michael D. (Las Vegas, NV); Klapperick, Robert L. (Las Vegas, NV); Bell, Chris (Las Vegas, NV)

1993-01-01T23:59:59.000Z

200

Aerosol can waste disposal device  

DOE Patents (OSTI)

Disclosed is a device for removing gases and liquid from containers. The device punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container. 7 figures.

O' Brien, M.D.; Klapperick, R.L.; Bell, C.

1993-12-21T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

NONE

1996-08-01T23:59:59.000Z

202

Disposal Authorization Statement | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and closure of the SDF, and is a requirement under the Department of Energy's (DOE) Radioactive Waste Management Manual 435.1-1. Disposal Authorization Statement More...

203

Operational Issues at the Environmental Restoration Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ERDF is operated by Stoller Corporation (Stoller) under subcontract to Washington Closure Hanford (WCH). Currently, six disposal cells comprise the ERDF, with four more...

204

Date: ____________ MATERIAL FOR HAZARDOUS WASTE DISPOSAL  

E-Print Network (OSTI)

Feb 2003 Date: ____________ MATERIAL FOR HAZARDOUS WASTE DISPOSAL 1) Source: Bldg: ________________________________________ Disinfection? cc YES, Autoclaved (each container tagged with `Treated Biomedical Waste') cc YES, Chemical

Sinnamon, Gordon J.

205

Used Fuel Disposition Campaign Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

206

Chemical Disposal The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program  

E-Print Network (OSTI)

Chemical Disposal Dec, 2011 Chemicals: The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program where all University chemical waste is picked up and sent out for proper disposal. (There are some chemicals that they will not take because of their extreme hazards

Machel, Hans

207

Petroleum Engineering Techniques for HLW Disposal  

Science Conference Proceedings (OSTI)

This paper describes why petroleum engineering techniques are of importance and can be used for underground disposal of HLW (high-level radioactive waste). It is focused on rock salt as a geological host medium in combination with disposal of the HLW canisters in boreholes drilled from the surface. Both permanent disposal and disposal with the option to retrieve the waste are considered. The paper starts with a description of the disposal procedure. Next disposal in deep boreholes is treated. Then the possible use of deviated boreholes and of multiple boreholes is discussed. Also waste isolation aspects and the implications of the HLW heat generation are treated. It appears that the use of deep boreholes can be beneficial, and also that--to a certain extent--borehole deviation offers possibilities. The benefits of using multiple boreholes are questionable for permanent disposal, while this technique cannot be applied for retrievable disposal. For the use of casing material, the additional temperature rise due to the HLW heat generation must be taken into account.

van den Broek, W. M. G. T.

2002-02-25T23:59:59.000Z

208

? Disposal concepts (ďenclosedĒ): crystalline, clay/shale,  

E-Print Network (OSTI)

salt, deep borehole (Re: January, 2012 briefing) ? Thermal analysis for mined, ďenclosed Ē concepts ? Finite element analysis for generic salt repository (waste package size up to 32-PWR) ? ďOpen Ē disposal concept development: shale unbackfilled, sedimentary backfilled, and hard-rock unsaturated (waste package sizes up to 32-PWR) ? Thermal analysis for mined, ďopen Ē concepts ? Cost estimation for 5 disposal concepts ? Summary and conclusions

Ernest Hardin (snl; Jim Blink; Harris Greenberg (llnl; Joe Carter (srnl; Rob Howard (ornl

2012-01-01T23:59:59.000Z

209

Evaluation of waste disposal by shale fracturing  

SciTech Connect

The shale fracturing process is evaluated as a means for permanent disposal of radioactive intermediate level liquid waste generated at the Oak Ridge National Laboratory. The estimated capital operating and development costs of a proposed disposal facility are compared with equivalent estimated costs for alternative methods of waste fixation.

Weeren, H.O.

1976-02-01T23:59:59.000Z

210

Land Management and Disposal | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Land Management and Disposal Land Management and Disposal Land Management and Disposal Land Management and Disposal 42 USC 2201(g), Section 161(g), of the AEA 42 USC Section 2224, Section 174 DOE, July 2004, Real Property Desk Guide Requirements: Document Title P.L. 83-703 (68 Stat. 919), Section 161g Grants Special Authority as Required in the Act to Acquire, Sell, Dispose, etc., of Real Property in Furtherance of the Department's Mission (Under the Atomic Energy Act of 1954) P.L. 95-91, 91 Stat. 578 (Sections 302 and 347) Department of Energy Organizational Act of 1977, Delegated Authority for Real Property P.L. 106-580 Federal Property and Administrative Services Act of 1949, As Amended P.L. 105-85 Federal Property and Administrative Services Act of 1949, As Amended 10 CFR 770 Transfer of Real Property at Defense Nuclear Facilities for Economic Development

211

Basis for Identification of Disposal Options for R and D for Spent Nuclear  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis for Identification of Disposal Options for R and D for Spent Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered barrier, and the waste. Salt, clay/shale, and granitic rocks represent a reasonable cross-section of behavior. Granitic rocks are also the primary basement rock to consider for deep borehole disposal. UFD is developing generic system analysis capability and general experimental data related to mined geologic disposal in the three

212

Combination gas producing and waste-water disposal well  

DOE Patents (OSTI)

The present invention is directed to a waste-water disposal system for use in a gas recovery well penetrating a subterranean water-containing and methane gas-bearing coal formation. A cased bore hole penetrates the coal formation and extends downwardly therefrom into a further earth formation which has sufficient permeability to absorb the waste water entering the borehole from the coal formation. Pump means are disposed in the casing below the coal formation for pumping the water through a main conduit towards the water-absorbing earth formation. A barrier or water plug is disposed about the main conduit to prevent water flow through the casing except for through the main conduit. Bypass conduits disposed above the barrier communicate with the main conduit to provide an unpumped flow of water to the water-absorbing earth formation. One-way valves are in the main conduit and in the bypass conduits to provide flow of water therethrough only in the direction towards the water-absorbing earth formation.

Malinchak, Raymond M. (McKeesport, PA)

1984-01-01T23:59:59.000Z

213

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER  

SciTech Connect

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this analysis is to support Site Recommendation reports and to assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the Development Plan ''Design Analysis for the Defense High-Level Waste Disposal Container'' (CRWMS M&O 2000c) with no deviations from the plan.

G. Radulesscu; J.S. Tang

2000-06-07T23:59:59.000Z

214

Large Component Removal/Disposal  

Science Conference Proceedings (OSTI)

This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

Wheeler, D. M.

2002-02-27T23:59:59.000Z

215

Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)  

SciTech Connect

New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

Cook, J

2005-05-26T23:59:59.000Z

216

Gas, Heat, Water, Sewerage Collection and Disposal, and Street...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies...

217

DOE - Office of Legacy Management -- Estes Gulch Disposal Cell...  

Office of Legacy Management (LM)

Estes Gulch Disposal Cell - 010 FUSRAP Considered Sites Site: Estes Gulch Disposal Cell (010) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

218

DOE - Office of Legacy Management -- Burro Canyon Disposal Cell...  

Office of Legacy Management (LM)

Burro Canyon Disposal Cell - 007 FUSRAP Considered Sites Site: Burro Canyon Disposal Cell (007) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

219

Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of Long-Term Performance Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of...

220

Idaho CERCLA Disposal Facility at Idaho National Laboratory ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho CERCLA Disposal Facility at Idaho National Laboratory Idaho CERCLA Disposal Facility at Idaho National Laboratory Full Document and Summary Versions are available for...

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Erosion Control and Revegetation at DOE's Lowman Disposal Site...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and...

222

Biological Weed Control at the Sherwood, Washington, Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services Ecosystem Management Team Biological Weed Control at the Sherwood, Washington, Disposal Site Biological Weed Control at the Sherwood, Washington, Disposal Site...

223

Acquisition, Use, and Disposal of Real Estate | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Use, and Disposal of Real Estate More Documents & Publications Acquisition, Use, and Disposal of Real Estate OPAM Policy Acquisition Guides Chapter 17 - Special Contracting Methods...

224

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste...

225

EA-1097: Solid waste Disposal - Nevada Test Site, Nye County...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7: Solid waste Disposal - Nevada Test Site, Nye County, Nevada EA-1097: Solid waste Disposal - Nevada Test Site, Nye County, Nevada SUMMARY This EA evaluates the environmental...

226

New Facility Will Test Disposal Cell Cover Renovation | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services Ecosystem Management Team New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation Calibration Facilities...

227

Solid Waste Disposal, Hazardous Waste Management Act, Underground...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Eligibility...

228

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect

The current baseline plan for RH TRU (remote-handled transuranic) waste disposal is to package the waste in special canisters for emplacement in the walls of the waste disposal rooms at the Waste Isolation Pilot Plant (WIPP). The RH waste must be emplaced before the disposal rooms are filled by contact-handled waste. Issues which must be resolved for this plan to be successful include: (1) construction of RH waste preparation and packaging facilities at large-quantity sites; (2) finding methods to get small-quantity site RH waste packaged and certified for disposal; (3) developing transportation systems and characterization facilities for RH TRU waste; (4) meeting lag storage needs; and (5) gaining public acceptance for the RH TRU waste program. Failure to resolve these issues in time to permit disposal according to the WIPP baseline plan will force either modification to the plan, or disposal or long-term storage of RH TRU waste at non-WIPP sites. The recommended strategy is to recognize, and take the needed actions to resolve, the open issues preventing disposal of RH TRU waste at WIPP on schedule. It is also recommended that the baseline plan be upgraded by adopting enhancements such as revised canister emplacement strategies and a more flexible waste transport system.

Bild, R.W. [Sandia National Lab., Albuquerque, NM (United States). Program Integration Dept.

1994-07-01T23:59:59.000Z

229

Spent fuel characteristics & disposal considerations  

SciTech Connect

The fuel used in commercial nuclear power reactors is uranium, generally in the form of an oxide. The gas-cooled reactors developed in England use metallic uranium enclosed in a thin layer of Magnox. Since this fuel must be processed into a more stable form before disposal, we will not consider the characteristics of the Magnox spent fuel. The vast majority of the remaining power reactors in the world use uranium dioxide pellets in Zircaloy cladding as the fuel material. Reactors that are fueled with uranium dioxide generally use water as the moderator. If ordinary water is used, the reactors are called Light Water Reactors (LWR), while if water enriched in the deuterium isotope of hydrogen is used, the reactors are called Heavy Water reactors. The LWRs can be either pressurized reactors (PWR) or boiling water reactors (BWR). Both of these reactor types use uranium that has been enriched in the 235 isotope to about 3.5 to 4% total abundance. There may be minor differences in the details of the spent fuel characteristics for PWRs and BWRs, but for simplicity we will not consider these second-order effects. The Canadian designed reactor (CANDU) that is moderated by heavy water uses natural uranium without enrichment of the 235 isotope as the fuel. These reactors run at higher linear power density than LWRs and produce spent fuel with lower total burn-up than LWRs. Where these difference are important with respect to spent fuel management, we will discuss them. Otherwise, we will concentrate on spent fuel from LWRs.

Oversby, V.M.

1996-06-01T23:59:59.000Z

230

The Salt Defense Disposal Investigations (SDDI)  

NLE Websites -- All DOE Office Websites (Extended Search)

Salt Defense Disposal Investigations (SDDI) Salt Defense Disposal Investigations (SDDI) will utilize a newly mined Underground Research Lab (URL) in WIPP to perform a cost effective, proof-of-principle field test of the emplacement of heat-generating radioactive waste and validate modeling efforts. The goals of the SDDI Thermal Test are to: * Demonstrate a proof-of-principle concept for in-drift disposal in salt. * Investigate, in a specific emplacement concept, the response of the salt to heat. * Develop a full-scale response for run-of- mine (ROM) salt. * Develop a validated coupled process model for disposal of heat-generating wastes in salt. * Evaluate the environmental conditions of the

231

Acquisition, Use, and Disposal of Real Estate  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Chapter 17.3 (March 2011) Chapter 17.3 (March 2011) 1 Acquisition, Use, and Disposal of Real Estate References DEAR 917.74 - Acquisition, Use, and Disposal of Real Estate DOE Directives DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets, or current version DOE Order 430.1B, Real Property Asset Management, or current version Overview This section provides internal Departmental information and DOE and NNSA points of contact for issues dealing with real estate acquisition, use, and disposal for cost reimbursement and fixed price contracts when in performance of the contract, the contractor will acquire or proposes to acquire use of real property. Background DEAR Subpart 917.74 - Acquisition, Use, and Disposal of Real Estate provides the policy and

232

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

2000-06-01T23:59:59.000Z

233

Waste disposal options report. Volume 2  

SciTech Connect

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01T23:59:59.000Z

234

Method of Disposing of Corrosive Gases  

DOE Patents (OSTI)

Waste gas containing elemental fluorine is disposed of in the disclosed method by introducing the gas near the top of a vertical chamber under a downward spray of caustic soda solution which contains a small amount of sodium sulfide.

Burford, W.B. III; Anderson, H.C.

1950-07-11T23:59:59.000Z

235

Economic assessment of CO? capture and disposal  

E-Print Network (OSTI)

A multi-sector multi-region general equilibrium model of economic growth and emissions is used to explore the conditions that will determine the market penetration of CO2 capture and disposal technology.

Eckaus, Richard S.; Jacoby, Henry D.; Ellerman, A. Denny.; Leung, Wing-Chi.; Yang, Zili.

236

A disposable, self-administered electrolyte test  

E-Print Network (OSTI)

This thesis demonstrates the novel concept that it is possible to make a disposable, self-administered electrolyte test to be introduced to the general consumer market. Although ion specific electrodes have been used to ...

Prince, Ryan, 1977-

2003-01-01T23:59:59.000Z

237

Scenarios of the TWRS low-level waste disposal program. Revision 1  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pre-treating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1995-01-01T23:59:59.000Z

238

Optimal evaluation of infectious medical waste disposal companies using the fuzzy analytic hierarchy process  

SciTech Connect

Ever since Taiwan's National Health Insurance implemented the diagnosis-related groups payment system in January 2010, hospital income has declined. Therefore, to meet their medical waste disposal needs, hospitals seek suppliers that provide high-quality services at a low cost. The enactment of the Waste Disposal Act in 1974 had facilitated some improvement in the management of waste disposal. However, since the implementation of the National Health Insurance program, the amount of medical waste from disposable medical products has been increasing. Further, of all the hazardous waste types, the amount of infectious medical waste has increased at the fastest rate. This is because of the increase in the number of items considered as infectious waste by the Environmental Protection Administration. The present study used two important findings from previous studies to determine the critical evaluation criteria for selecting infectious medical waste disposal firms. It employed the fuzzy analytic hierarchy process to set the objective weights of the evaluation criteria and select the optimal infectious medical waste disposal firm through calculation and sorting. The aim was to propose a method of evaluation with which medical and health care institutions could objectively and systematically choose appropriate infectious medical waste disposal firms.

Ho, Chao Chung, E-mail: ho919@pchome.com.tw [Department of Industrial Management, National Taiwan University of Science and Technology, Taipei, Taiwan (China)

2011-07-15T23:59:59.000Z

239

Flexible on-chip power delivery for energy efficient heterogeneous systems  

Science Conference Proceedings (OSTI)

Heterogeneous systems-on-chip pose a challenge for power delivery given the variety of needs for different components. In this paper, we describe recent work that leverages power switches and conventional EDA toolflows to implement a set of power delivery ... Keywords: PDVS, dynamic voltage scaling, leakage, low power design, variable weighted headers

Benton H. Calhoun, Kyle Craig

2013-05-01T23:59:59.000Z

240

Clean Cities: National Clean Fleets Partner: Advanced Disposal Services  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Advanced Disposal Services to someone by E-mail Share Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Facebook Tweet about Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Twitter Bookmark Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Google Bookmark Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Delicious Rank Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Digg Find More places to share Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on AddThis.com... Goals & Accomplishments Partnerships National Clean Fleets Partnership National Parks Initiative Electric Vehicle Infrastructure Training Program Advanced Vehicle Technology Competitions

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

THE DISPOSAL OF POWER REACTOR WASTE INTO DEEP WELLS  

SciTech Connect

Disposal of wastes from the processing of solid fuel elements and from solid blanket elements is discussed. The subjects considered include extraction of uranium by several methods, the removal of element jackets, the treatment of uraxium -zirconium fuel elements, disposal into deep wells, the hydraulics of wells, thermal considerations of disposal aquifers regional hydrology, potential deep-well disposal areas in the U. S., aud the cost of disposal. (J.R.D.)

de Laguna, W.; Blomeke, J.O.

1957-06-13T23:59:59.000Z

242

The feasibility of deep well injection for brine disposal  

E-Print Network (OSTI)

A generalized methodology for evaluating the technical feasibility of projects involving the disposal of waste brine by injection into deep saline aquifers is developed, primarily from the hydrology and petroleum engineering literature. Data collection, groundwater modeling, and fluid compatibility are discussed in detail. Injection system design, economics, and regulatory considerations are more related to economic than technical feasibility, and are discussed only as they relate to technical feasibility. The methodology is utilized to make a preliminary evaluation of a proposed brine injection project in the Dove Creek area of King and Stonewall Counties, North Central Texas. Four known deep aquifers are modeled, using the SWIFT/486 software, to determine their ability to receive two cfs of brine for a project life of one hundred years. Two aquifers, the Strawn and EUenburger Formations, are predicted to be acceptable for disposal. Each aquifer would require only one disposal well which is favorable for the economics of the project. Additional data, particularly hydraulic conductivity and net aquifer thickness data, are required to make a more definitive technical feasibility determination for this project.

Spongberg, Martin Edward

1994-01-01T23:59:59.000Z

243

Proceedings of the 1981 subseabed disposal program. Annual workshop  

Science Conference Proceedings (OSTI)

The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal.

Not Available

1982-01-01T23:59:59.000Z

244

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY  

SciTech Connect

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

245

Microsoft Word - SRSSaltWasteDisposal.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Salt Waste Disposal - References - §3116 Determination (RWR NDAA of 2005) Salt Waste Disposal - References - §3116 Determination (RWR NDAA of 2005) Doc. No. Filename Title Main Document References 1. 2005 RWR DAA §3116 NDAA.pdf "Ronald W. Regan National Defense Authorization Act for FY 2005," Section 3116, 2004. 2. CBU-PIT-2004-00024 CBU-PIT-2004-00024.pdf Ledbetter, L. S., CBU-PIT-2004-00024, 12/01/04 - December Monthly WCS Curie and Volume Inventory Report," Revision 0, December 9, 2004. 3. CBU-PIT-2005-00031 CBU-PIT-2005-00031.pdf Rios-Armstrong, M. A., CBU-PIT-2005-00031, "Decontaminated Salt Solution Volume to be transferred to the Saltstone Disposal Facility from Salt Treatment and Disposition Activities," Revision 0, February 13, 2005.

246

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect

We have developed a phased strategy that defines specific program-management activities and critical documentation for producing radioactive waste forms, from pyrochemical processing of spent nuclear fuel, that will be acceptable for geologic disposal by the US Department of Energy. The documentation of these waste forms begins with the decision to develop the pyroprocessing technology for spent fuel conditioning and ends with production of the last waste form for disposal. The need for this strategy is underscored by the fact that existing written guidance for establishing the acceptability for disposal of radioactive waste is largely limited to borosilicate glass forms generated from the treatment of aqueous reprocessing wastes. The existing guidance documents do not provide specific requirements and criteria for nonstandard waste forms such as those generated from pyrochemical processing operations.

Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Laidler, J.J.; McPheeters, C.C. [Argonne National Lab., IL (United States)

1994-09-01T23:59:59.000Z

247

Environmental restoration waste materials co-disposal  

Science Conference Proceedings (OSTI)

Co-disposal of radioactive and hazardous waste is a highly efficient and cost-saving technology. The technology used for final treatment of soil-washing size fractionization operations is being demonstrated on simulated waste. Treated material (wasterock) is used to stabilize and isolate retired underground waste disposal structures or is used to construct landfills or equivalent surface or subsurface structures. Prototype equipment is under development as well as undergoing standardized testing protocols to prequalify treated waste materials. Polymer and hydraulic cement solidification agents are currently used for geotechnical demonstration activities.

Phillips, S.J.; Alexander, R.G.; England, J.L.; Kirdendall, J.R.; Raney, E.A.; Stewart, W.E. [Westinghouse Hanford Co., Richland, WA (United States); Dagan, E.B.; Holt, R.G. [Dept. of Energy, Richland, WA (United States). Richland Operations Office

1993-09-01T23:59:59.000Z

248

Generic Deep Geologic Disposal Safety Case | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Deep Geologic Disposal Safety Case Deep Geologic Disposal Safety Case Generic Deep Geologic Disposal Safety Case The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW). Potential disposal options include mined disposal in a variety of geologic media (e.g., salt, shale, granite), and deep borehole disposal in basement rock. The Generic Safety Case is intended to be a source of information to provide answers to questions that may arise as the U.S. works to develop strategies to dispose of current and future inventories of UNF and HLW. DOE is examining combinations of generic geologic media and facility designs that could potentially support

249

Civilian Radioactive Waste Management System Requirements Document...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management System Requirements Document More Documents & Publications Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 FY 2007 Total...

250

Freeze resistant buoy system  

DOE Patents (OSTI)

A freeze resistant buoy system includes a tail-tube buoy having a thermally insulated section disposed predominantly above a waterline, and a thermo-siphon disposed predominantly below the waterline.

Hill, David E. (Knoxville, TN); Rodriguez, Jr., Miguel (Oak Ridge, TN); Greenbaum, Elias (Knoxville, TN); Klett, James W. (Knoxville, TN)

2007-08-21T23:59:59.000Z

251

Status of UFD Campaign International Activities in Disposal Research |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Status of UFD Campaign International Activities in Disposal Status of UFD Campaign International Activities in Disposal Research Status of UFD Campaign International Activities in Disposal Research Several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics (clay/shale, granite), most of which were very different from those studied in the United States. The DOE recognizes that close international collaboration is a beneficial and cost effective strategy for advancing disposal science. This report describes the active collaboration opportunities available to U.S. researchers, and presents specific cooperative research activities that have been recently initiated within DOE's disposal research program.

252

Process for the disposal of alkali metals  

SciTech Connect

Large quantities of alkali metals may be safely reacted for ultimate disposal by contact with a hot concentrated caustic solution. The alkali metals react with water in the caustic solution in a controlled reaction while steam dilutes the hydrogen formed by the reaction to a safe level.

Lewis, Leroy C. (Arco, ID)

1977-01-01T23:59:59.000Z

253

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS  

SciTech Connect

The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

THIELGES, J.R.; CHASTAIN, S.A.

2007-06-21T23:59:59.000Z

254

A disposable capillary electrophoresis microchip with an indium tin oxide decoupler/amperometric detector  

Science Conference Proceedings (OSTI)

We have fabricated a capillary electrophoresis (CE) chip-based electrochemical detection (ECD) system for measurements of the dopamine, catechol, DNA ladder, and hydrogen peroxide, respectively. The microfabricated CE-ECD systems are adequate for a disposable ... Keywords: Capillary electrophoresis, Electrochemical detection, ITO, Microchip, PDMS

Ju-Ho Kim; C. J. Kang; D. Jeon; Yong-Sang Kim

2005-03-01T23:59:59.000Z

255

Low-Level Waste Disposal Facility Federal Review Group Manual  

Energy.gov (U.S. Department of Energy (DOE))

This Revision 3 of the Low-Level Waste Disposal† Facility Federal Review Group (LFRG) Manual was prepared primarily to include review criteria for the review of transuranic (TRU) waste disposal...

256

Strategy for the Management and Disposal of Used Nuclear Fuel...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level...

257

Laboratory to demolish excavation enclosures at Material Disposal...  

NLE Websites -- All DOE Office Websites (Extended Search)

waste disposal facility. MDA B was used from 1944 to 1948 as a waste disposal site for Manhattan Project and Cold War-era research and production. The Laboratory received 212...

258

UCSC Glassware and Sharps Disposal Matrix Responsibility Color key  

E-Print Network (OSTI)

(Solid Debris) EH&S Lab Safety Services Dispose of Sharps Safely! Includes syringes (with or without debris may be combined. Dispose by completing a Radioactive Waste Tracking Form and affix to the box

California at Santa Cruz, University of

259

Disposal Practices at the Nevada Test Site 2008 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at the Nevada Test Site 2008...

260

Drilling Systems | Open Energy Information  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon ¬Ľ Drilling Systems Jump to: navigation, search Contents 1 Geothermal Lab Call Projects for Drilling Systems 2 Geothermal ARRA Funded Projects for Drilling Systems Geothermal Lab Call Projects for Drilling Systems Loading map... {"format":"googlemaps3","type":"ROADMAP","types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"limit":200,"offset":0,"link":"all","sort":[""],"order":[],"headers":"show","mainlabel":"","intro":"","outro":"","searchlabel":"\u2026

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Disposable Point-of-Care Testing Device for Nucleic Acid ...  

home \\ technologies \\ disposable point of care testing device. Technologies: Ready-to-Sign Licenses: ... Operated by Lawrence Livermore National Security, ...

262

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

Energy.gov (U.S. Department of Energy (DOE))

Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal† Facility Performance Assessments and Composite Analyses

263

Idaho CERCLA Disposal Facility at Idaho National Laboratory ...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facility at Idaho National Laboratory Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory More Documents & Publications Environmental Management...

264

Integrated Used Nuclear Fuel Storage, Transportation, and Disposal ...  

dry cask storage of used nuclear fuel at existing plant ... achievement of geologic disposal thermal management ... Senior Technology Commercialization Manager ...

265

Materials for Nuclear Waste Disposal and Environmental Cleanup  

Science Conference Proceedings (OSTI)

Symposium, Materials for Nuclear Waste Disposal and Environmental Cleanup ... Secure and Certify Studies to Work on Production of Spiked Plutonium.

266

Acceptance of Classified Excess Components for Disposal at Area 5  

Science Conference Proceedings (OSTI)

This slide-show discusses weapons dismantlement and disposal, issues related to classified waste and their solutions.

Poling, J., and Saad, M.

2012-04-09T23:59:59.000Z

267

CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY  

SciTech Connect

As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

Jordan, J.; Flach, G.

2012-03-29T23:59:59.000Z

268

Design requirements document for project W-520, immobilized low-activity waste disposal  

SciTech Connect

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Ashworth, S.C.

1998-08-06T23:59:59.000Z

269

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal  

Science Conference Proceedings (OSTI)

As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For example, the excavation-damaged zone (EDZ) near repository tunnels can modify local permeability (resulting from induced fractures), potentially leading to less confinement capability (Tsang et al., 2005). Because of clay's swelling and shrinkage behavior (depending on whether the clay is in imbibition or drainage processes), fracture properties in the EDZ are quite dynamic and evolve over time as hydromechanical conditions change. To understand and model the coupled processes and their impact on repository performance is critical for the defensible performance assessment of a clay repository. Within the Natural Barrier System (NBS) group of the Used Fuel Disposition (UFD) Campaign at DOE's Office of Nuclear Energy, LBNL's research activities have focused on understanding and modeling such coupled processes. LBNL provided a report in this April on literature survey of studies on coupled processes in clay repositories and identification of technical issues and knowledge gaps (Tsang et al., 2010). This report will document other LBNL research activities within the natural system work package, including the development of constitutive relationships for elastic deformation of clay rock (Section 2), a THM modeling study (Section 3) and a THC modeling study (Section 4). The purpose of the THM and THC modeling studies is to demonstrate the current modeling capabilities in dealing with coupled processes in a potential clay repository. In Section 5, we discuss potential future R&D work based on the identified knowledge gaps. The linkage between these activities and related FEPs is presented in Section 6.

Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

2010-08-31T23:59:59.000Z

270

Environmental Assessment Photovoltaic Solar Project at the Durango, Colorado, Disposal Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of Energy Office of Legacy Management U.S. Department of Energy Office of Legacy Management DOE/EA 1770 FINDING OF NO SIGNIFICANT IMPACT Photovoltaic Solar Project at the Durango, Colorado, Disposal Site, La Plata County AGENCY: U.S. Department of Energy (DOE), Office of Legacy Management (LM) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: LM prepared an Environmental Assessment (EA) (DOE/EA-1770) that evaluated two action alternatives related to the installation, operation, and removal of a photovoltaic (PV) solar energy system on the Durango, Colorado, Disposal Site and the No Action Alternative. Alternative 1 evaluated the use of the 18-acre (ac) vegetated surface of the disposal cell for the installation of a PV system. The second action alternative (Alternative 2, the Preferred Action) considered the use of the surface of the

271

LEGACY NONCONFORMANCE ISSUE IN SOLID WASTE DISPOSAL  

Science Conference Proceedings (OSTI)

Beginning in 1968 waste from sectioning, sampling, and assaying of reactor fuels was sent to underground burial caissons in the 200-W Area of the Hanford Plant in Richland, Washington. In 2002 a review of inventory records revealed that criticality safety storage limits had been exceeded. This prompted declaration of a Criticality Prevention Specification nonconformance. The corrective action illustrates the difficulties in demonstrating compliance to fissile material limits decades after waste disposal.

ROGERS, C.A.

2002-12-16T23:59:59.000Z

272

The Determinants of Hazardous Waste Disposal Choice:  

E-Print Network (OSTI)

In this paper, we estimate conditional logit models of generatorís choice of waste management facilities (TSDFs) for shipments of halogenated solvent waste documented by the manifests filled out in California in 1995. We find that the probability that a facility is selected as the destination of an off-site shipment of halogenated solvent waste depends on the cost of shipping and disposal at that facility, on measures of existing contamination at the site, and on the track record of the receiving facility. Generators do seem to balance current disposal costs with the likelihood of future liability, should the TSDF become involved in either the state or federal Superfund program. In general, we find no evidence that generators prefer ďwealthier Ē TSDFs or ďlarger Ē facilities, suggesting that there is a role for smaller, private companies in the management of halogenated solvent waste. When attention is limited to so-called ďrestricted Ē wastes containing halogenated compounds, which cannot be landfilled, the best match between the waste and the treatment offered by the facility may be more important than saving on the cost of disposal, and price may even be interpreted as a signal for quality of the facility. 3

Anna Alberini; John Bartholomew; Anna Alberini; John Bartholomew

1998-01-01T23:59:59.000Z

273

MANAGING UNCERTAINTIES ASSOCIATED WITH RADIOACTIVE WASTE DISPOSAL: TASK GROUP 4 OF THE IAEA PRISM PROJECT  

Science Conference Proceedings (OSTI)

It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

Seitz, R.

2011-03-02T23:59:59.000Z

274

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site May 15, 2013 - 12:00pm Addthis A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. Macro-packs from the Idaho site are shown here safely and compliantly disposed. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. IDAHO FALLS, Idaho - An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for

275

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility June 6, 2013 - 12:00pm Addthis The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. ANDREWS, Texas - DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind. EM Senior Advisor Dave Huizenga and several other federal, state and local officials attended the event at Waste Control Specialists (WCS) in Andrews and witnessed the first container being placed in the new state-of-the-art facility. WCS is a waste processing and disposal company. "I am proud to be here today to celebrate this historic event. We

276

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site May 15, 2013 - 12:00pm Addthis A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. Macro-packs from the Idaho site are shown here safely and compliantly disposed. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. IDAHO FALLS, Idaho - An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for

277

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Applauds Opening of Historic Disposal Facility Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility June 6, 2013 - 12:00pm Addthis The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. ANDREWS, Texas - DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind. EM Senior Advisor Dave Huizenga and several other federal, state and local officials attended the event at Waste Control Specialists (WCS) in Andrews and witnessed the first container being placed in the new state-of-the-art facility. WCS is a waste processing and disposal company. "I am proud to be here today to celebrate this historic event. We

278

Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE Issues Statement Concerning Debates Over DOE Issues Statement Concerning Debates Over Waste Disposal in Salt CARLSBAD, N.M., July 24, 2009 - The U.S. Department of Energy and its Carlsbad Field Office recognize and respect the long history that led to the current regulations that govern operations at the Waste Isolation Pilot Plant (WIPP). The WIPP is authorized to ship and dispose of transuranic (TRU) waste that was created by U.S. defense programs. TRU waste is a category of waste strictly defined by legislation and legal agreements. The WIPP mission includes the safe disposal of two types of defense-related TRU waste, contact-handled (CH) and remote-handled (RH). Both consist of tools, rags, protective clothing, sludges, soil and other materials contaminated with radioactive

279

Radiological Surveys Performed in Support of the Demolition and Bulk Disposal Decommissioning Method  

SciTech Connect

Connecticut Yankee Atomic Power Company is decommissioning the Haddam Neck Plant using the 'Demolition and Bulk Disposal' method, or commonly referred to as 'Rip and Ship'. In general, completing the project using this method entails the removal of all irradiated fuel and highly contaminated systems and components, and the subsequent demolition of the above ground portions of most site structures. Since most structures are removed from site, cost and time savings are realized by virtually eliminating the need for remediation. However, this method of decommissioning creates more waste, both radiological and non-radiological, which must be segregated, packaged and disposed of properly. Prior to demolition, various types of radiological surveys must be performed and work controls put into place to minimize the spread of contamination to other areas of the site, and to prevent the inadvertent release of radioactive materials from the site. This paper will discuss the various types of radiological surveys performed, and controls implemented, in support of the demolition and bulk material disposal decommissioning method, with the emphasis on pre-demolition surveys. Details will be provided on the release criteria, survey design, survey implementation and data analysis on each of the various surveys, as well as a discussion on the controls implemented to prevent the various wastes from inadvertently being shipped to an inappropriate disposal facility. This paper will also strive to provide lessons learned for future projects that utilize the demolition and bulk disposal decommissioning method. (authors)

Yetter, R.F. [Babcock Services, Inc., 1840 Terminal Drive, Richland, WA 99352 (United States); Newson, C.T. [Connecticut Yankee Atomic Power Company, 362 Injun Hollow Road, East Hampton, CT 06424 (United States)

2006-07-01T23:59:59.000Z

280

200 Area Treated Effluent Disposal Facility operational test specification. Revision 2  

Science Conference Proceedings (OSTI)

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met. The technical requirements for operational testing of the 200 Area TEDF are defined by the test requirements presented in Appendix A. These test requirements demonstrate the following: pump station No.1 and associated support equipment operate both automatically and manually; pump station No. 2 and associated support equipment operate both automatically and manually; water is transported through the collection and transfer lines to the disposal ponds with no detectable leakage; the disposal ponds accept flow from the transfer lines with all support equipment operating as designed; and the control systems operate and status the 200 Area TEDF including monitoring of appropriate generator discharge parameters.

Crane, A.F.

1995-02-09T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

RESIDUES FROM COAL CONVERSION AND UTILIZATION: ADVANCED MINERALOGICAL CHARACTERIZATION AND DISPOSED BYPRODUCT DIAGENESIS  

SciTech Connect

The goals of the project are two-fold: (1) to upgrade semi-quantitative X-ray diffraction (QXRD) methods presently used in analyzing complex coal combustion by-product (CCB) systems, with the quantitative Rietveld method, and (2) to apply this method to a set of by-product materials that have been disposed or utilized for a long period (5 years or more) in contact with the natural environment, to further study the nature of CCB diagenesis. The project is organized into three tasks to accomplish these two goals: (1) thorough characterization of a set of previously analyzed disposed by-product materials, (2) development of a set of CCB-specific protocols for Rietveld QXRD, and (3) characterization of an additional set of disposed CCB materials, including application of the protocols for Rietveld QXRD developed in Task 2.

Gregory J. McCarthy; Dean G. Grier

1998-09-01T23:59:59.000Z

282

Review of Yucca Mountain Disposal Criticality Studies  

SciTech Connect

The U.S. Department of Energy (DOE), Office of Civilian Radioactive Waste Management, submitted a license application for construction authorization of a deep geologic repository at Yucca Mountain, Nevada, in June of 2008. The license application is currently under review by the U.S. Nuclear Regulatory Commission. However,on March 3, 2010 the DOE filed a motion requesting withdrawal of the license application. With the withdrawal request and the development of the Blue Ribbon Commission to seek alternative strategies for disposing of spent fuel, the status of the proposed repository at Yucca Mountain is uncertain. What is certain is that spent nuclear fuel (SNF) will continue to be generated and some long-lived components of the SNF will eventually need a disposition path(s). Strategies for the back end of the fuel cycle will continue to be developed and need to include the insights from the experience gained during the development of the Yucca Mountain license application. Detailed studies were performed and considerable progress was made in many key areas in terms of increased understanding of relevant phenomena and issues regarding geologic disposal of SNF. This paper reviews selected technical studies performed in support of the disposal criticality analysis licensing basis and the use of burnup credit. Topics include assembly misload analysis, isotopic and criticality validation, commercial reactor critical analyses, loading curves, alternative waste package and criticality control studies, radial burnup data and effects, and implementation of a conservative application model in the criticality probabilistic evaluation as well as other information that is applicable to operations regarding spent fuel outside the reactor. This paper summarizes the work and significant accomplishments in these areas and provides a resource for future, related activities.

Scaglione, John M [ORNL; Wagner, John C [ORNL

2011-01-01T23:59:59.000Z

283

Disposal R&D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration  

Science Conference Proceedings (OSTI)

For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

Birkholzer, J.T.

2011-06-01T23:59:59.000Z

284

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal Research and Development Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

285

Disposal Practices at the Nevada Test Site 2008  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Area 5 LLRW & MLLW Disposal Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive

286

Summary - Disposal Practices at the Nevada Test Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nevada Test Site, NV Nevada Test Site, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive waste (MLLW) are disposed of in Area 5 in shallow

287

DOE - Office of Legacy Management -- Maryland Disposal Site - MD 05  

Office of Legacy Management (LM)

Maryland Disposal Site - MD 05 Maryland Disposal Site - MD 05 FUSRAP Considered Sites Site: MARYLAND DISPOSAL SITE (MD.05 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Baltimore - Vicinity , Maryland MD.05-1 Evaluation Year: 1989 MD.05-1 Site Operations: Proposed disposal site - never developed. MD.05-1 Site Disposition: Eliminated Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to MARYLAND DISPOSAL SITE MD.05-1 - Report (DOE/OR/20722-131 Revision 0); Site Plan for the Maryland Disposal Site; April 1989 Historical documents may contain links which are no longer valid or to

288

Deep Borehole Disposal Research: Demonstration Site Selection Guidelines,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Deep Borehole Disposal Research: Demonstration Site Selection Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs The U.S. Department of Energy has been investigating deep borehole disposal as one alternative for the disposal of spent nuclear fuel and other radioactive waste forms, along with research and development for mined repositories in salt, granite, and clay, as part of the used fuel disposition (UFD) campaign. The deep borehole disposal concept consists of drilling a borehole on the order of 5,000 m deep, emplacing waste canisters in the lower part of the borehole, and sealing the upper part of the borehole with bentonite and concrete seals. A reference design of the

289

Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INL, Idaho INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Idaho CERCLA Disposal Facility (ICDF) At Idaho National Laboratory (INL) Why DOE-EM Did This Review The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose of LLW and MLW generated from remedial activities at the Idaho National Laboratory (INL). Components of the ICDF include a landfill that is used for disposal of solid waste, an evaporation pond that is used to manage leachate from the landfill and other aqueous wastes (8.3 million L capacity), and a staging and treatment facility. The ICDF is located near the southwest

290

LANL completes excavation of 1940s waste disposal site  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL completes excavation LANL completes excavation LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 22, 2011 Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation. Contact Colleen Curran Communicatons Office (505) 664-0344 Email LOS ALAMOS, New Mexico, September 22, 2011-Los Alamos National Laboratory has completed excavation of its oldest waste disposal site, Material Disposal Area B (MDA-B). The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. MDA-B was used from 1944-48 as a waste disposal site for Manhattan Project and Cold War-era research and

291

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

292

Low-Level Radioactive Waste Disposal Act (Pennsylvania) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Municipal/Public Utility Local Government Rural Electric Cooperative Transportation Program Info State Pennsylvania Program Type Environmental Regulations Provider Pennsylvania Department of Environmental Protection This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and storage of low-level radioactive waste. Commercial incineration of radioactive wastes is prohibited. Licenses are required for low-level radioactive waste disposal facilities not licensed to accept low-level radioactive waste. Disposal at

293

Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Low-Level Radioactive Waste Disposal Regional Facility Act Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Fees This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental Resources funds to be utilized for disposal facilities. This act ensures that nuclear facilities and the Department comply with the Low-Level Radioactive Disposal Act. The regional facility siting fund is used for reimbursement of expenses

294

B Plant treatment, storage, and disposal (TSD) units inspection plan  

Science Conference Proceedings (OSTI)

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements.

Beam, T.G.

1996-04-26T23:59:59.000Z

295

Long-length contaminated equipment disposal process path document  

Science Conference Proceedings (OSTI)

The first objective of the LLCE Process Path Document is to guide future users of this system on how to accomplish the cradle-to-grave process for the disposal of long-length equipment. Information will be provided describing the function and approach to each step in the process. Pertinent documentation, prerequisites, drawings, procedures, hardware, software, and key interfacing organizations will be identified. The second objective is related to the decision to lay up the program until funding is made available to complete it or until a need arises due to failure of an important component in a waste tank. To this end, the document will identify work remaining to be completed for each step of the process and open items or issues that remain to be resolved.

McCormick, W.A.

1998-09-30T23:59:59.000Z

296

Nevada test site experience with greater confinement disposal  

Science Conference Proceedings (OSTI)

At the NTS, we consider Greater Confinement Disposal (GCD) to be a good waste management practice rather than a disposal technology. This is an important distinction because it redefines the nature of GCD. All disposal facilities operate under the principal of ''as low as reasonably achievable'' (ALARA) in reducing personnel and public exposures. ALARA is not a technology or method but a principal put into practice. We view GCD in the same manner.

Dickman, P.T.; Boland, J.R.

1986-01-01T23:59:59.000Z

297

Disposal Cost Savings Considerations in Curie Reduction Programs  

Science Conference Proceedings (OSTI)

In 1996, the Low Level Radioactive Waste (LLW) Disposal Facility in Barnwell, South Carolina, announced a new fee structure for the disposal of radioactive wastes based on waste density, dose rate, and activity (curies). This report provides a detailed discussion of the current Barnwell Disposal Fee Structure along with its cost impact on various types of wastes generated. The report also evaluates various curie reduction options, their practical application, and their cost savings potential to help LLW ...

1998-03-30T23:59:59.000Z

298

ERDA safety practices involving disposal of contaminated real property  

SciTech Connect

A general discussion of the specific procedures for excess disposal outlined in the Property Management Handbook, ERDAM 5301 is given. (LK)

Loop, E.K.

1975-09-01T23:59:59.000Z

299

IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS,...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Centers Field Sites Power Marketing Administration Other Agencies You are here Home IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS, IG-0527 IDAHO OPERATIONS OFFICE...

300

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

Energy.gov (U.S. Department of Energy (DOE))

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Used Fuel Disposition Campaign Disposal Research and Development...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF)...

302

Environmental Impacts of Options for Disposal of Depleted Uranium...  

NLE Websites -- All DOE Office Websites (Extended Search)

study by Oak Ridge National Laboratory evaluated the acceptability of several depleted uranium conversion products at potential LLW disposal sites to provide a basis for DOE...

303

Microsoft Word - SRSSaltWasteDisposal.doc | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site - Tank 48 SRS Review Report 2009 Performance Assessment for the Saltstone Disposal Facility DOE Order 435.1 Performance Assessment Savannah River Site...

304

Spent Fuel Disposal Trust Fund (Maine) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Type Safety and Operational Guidelines Any licensee operating a nuclear power plant in this State shall establish a segregated Spent Nuclear Fuel Disposal Trust Fund...

305

Low-Level Waste Disposal Alternatives Analysis Report  

SciTech Connect

This report identifies and compares on-site and off-site disposal options for the disposal of contract-handled and remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Potential disposal options are screened for viability by waste type resulting in a short list of options for further consideration. The most crediable option are selected after systematic consideration of cost, schedule constraints, and risk. In order to holistically address the approach for low-level waste disposal, options are compiled into comprehensive disposal schemes, that is, alternative scenarios. Each alternative scenario addresses the disposal path for all low-level waste types over the period of interest. The alternative scenarios are compared and ranked using cost, risk and complexity to arrive at the recommended approach. Schedule alignment with disposal needs is addressed to ensure that all waste types are managed appropriately. The recommended alternative scenario for the disposal of low-level waste based on this analysis is to build a disposal facility at the Idaho National Laboratory Site.

Timothy Carlson; Kay Adler-Flitton; Roy Grant; Joan Connolly; Peggy Hinman; Charles Marcinkiewicz

2006-09-01T23:59:59.000Z

306

Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External...

307

Los Alamos Lab Completes Excavation of Waste Disposal Site Used...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Excavation of Waste Disposal Site Used in the 1940s More Documents & Publications Manhattan Project Truck Unearthed in Recovery Act Cleanup Protecting Recovery Act Cleanup...

308

NDAA Section 3116 Waste Determinations with Related Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste...

309

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

Hightower, J.R.; Trabalka, J.R.

2000-02-01T23:59:59.000Z

310

Solid Waste Disposal Facilities (Massachusetts) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Transportation Tribal Government Utility Program Info State Massachusetts Program Type Siting and Permitting Provider Department of Environmental Protection These sections articulate rules for the maintenance and operation of solid waste disposal facilities, as well as site assignment procedures. Applications for site assignment will be reviewed by the Massachusetts Department of Environmental Protection as well as the Department of Public

311

Carbon dioxide disposal in solid form  

SciTech Connect

Coal reserves can provide for the world`s energy needs for centuries. However, coal`s long term use may be severely curtailed if the emission of carbon dioxide into the atmosphere is not eliminated. We present a safe and permanent method of carbon dioxide disposal that is based on combining carbon dioxide chemically with abundant raw materials to form stable carbonate minerals. We discuss the availability of raw materials and potential process designs. We consider our initial rough cost estimate of about 3{cents}/kWh encouraging. The availability of a carbon dioxide fixation technology would serve as insurance in case global warming, or the perception of global warming, causes severe restrictions on carbon dioxide emissions. If the increased energy demand of a growing world population is to be satisfied from coal, the implementation of such a technology would quite likely be unavoidable.

Lackner, K.S.; Butt, D.P.; Sharp, D.H. [Los Alamos National Lab., NM (United States); Wendt, C.H. [Auxon Corp., (United States)

1995-12-31T23:59:59.000Z

312

Disposable sludge dewatering container and method  

DOE Patents (OSTI)

This invention is comprised of a device and method for preparing sludge for disposal comprising a box with a thin layer of gravel on the bottom and a thin layer of sand on the gravel layer, an array of perforated piping deployed throughout the gravel layer, and a sump in the gravel layer below the perforated piping array. Standpipes connect the array and sump to an external ion exchanger/fine particulate filter and a pump. Sludge is deposited on the sand layer and dewatered using a pump connected to the piping array, topping up with more sludge as the aqueous component of the sludge is extracted. When the box is full and the free standing water content of the sludge is acceptable, the standpipes are cut and sealed and the lid secured to the box.

Cole, C.M.

1990-12-27T23:59:59.000Z

313

LABORATORY EXPERIMENTS TO SIMULATE CO2 OCEAN DISPOSAL  

SciTech Connect

This Final Technical Report summarizes the technical accomplishments of an investigation entitled ''Laboratory Experiments to Simulate CO{sub 2} Ocean Disposal'', funded by the U.S. Department of Energy's University Coal Research Program. This investigation responds to the possibility that restrictions on greenhouse gas emissions may be imposed in the future to comply with the Framework Convention on Climate Change. The primary objective of the investigation was to obtain experimental data that can be applied to assess the technical feasibility and environmental impacts of oceanic containment strategies to limit release of carbon dioxide (CO{sub 2}) from coal and other fossil fuel combustion systems into the atmosphere. A number of critical technical uncertainties of ocean disposal of CO{sub 2} were addressed by performing laboratory experiments on liquid CO{sub 2} jet break-up into a dispersed droplet phase, and hydrate formation, under deep ocean conditions. Major accomplishments of this study included: (1) five jet instability regimes were identified that occur in sequence as liquid CO{sub 2} jet disintegration progresses from laminar instability to turbulent atomization; (2) linear regression to the data yielded relationships for the boundaries between the five instability regimes in dimensionless Ohnesorge Number, Oh, and jet Reynolds Number, Re, space; (3) droplet size spectra was measured over the full range of instabilities; (4) characteristic droplet diameters decrease steadily with increasing jet velocity (and increasing Weber Number), attaining an asymptotic value in instability regime 5 (full atomization); and (5) pre-breakup hydrate formation appears to affect the size distribution of the droplet phase primary by changing the effective geometry of the jet.

Stephen M. Masutani

1999-12-31T23:59:59.000Z

314

Evaluation of food waste disposal options by LCC analysis from the perspective of global warming: Jungnang case, South Korea  

SciTech Connect

Highlights: > Various food waste disposal options were evaluated from the perspective of global warming. > Costs of the options were compared by the methodology of life cycle assessment and life cycle cost analysis. > Carbon price and valuable by-products were used for analyzing environmental credits. > The benefit-cost ratio of wet feeding scenario was the highest. - Abstract: The costs associated with eight food waste disposal options, dry feeding, wet feeding, composting, anaerobic digestion, co-digestion with sewage sludge, food waste disposer, incineration, and landfilling, were evaluated in the perspective of global warming and energy and/or resource recovery. An expanded system boundary was employed to compare by-products. Life cycle cost was analyzed through the entire disposal process, which included discharge, separate collection, transportation, treatment, and final disposal stages, all of which were included in the system boundary. Costs and benefits were estimated by an avoided impact. Environmental benefits of each system per 1 tonne of food waste management were estimated using carbon prices resulting from CO{sub 2} reduction by avoided impact, as well as the prices of by-products such as animal feed, compost, and electricity. We found that the cost of landfilling was the lowest, followed by co-digestion. The benefits of wet feeding systems were the highest and landfilling the lowest.

Kim, Mi-Hyung, E-mail: mhkim9@snu.ac.kr [Department of Environmental Planning, Graduate School of Environmental Studies, Seoul National University, San 56-1, Sillim-Dong, Gwanak-Gu, Seoul 151-742 (Korea, Republic of); Song, Yul-Eum, E-mail: yesong0724@dongguk.edu [Department of Philosophy, Dongguk University, Pil-Dong 3-Ga, Jung-Gu, Seoul 100-715 (Korea, Republic of); Department of Life Science, Dongguk University, Pil-Dong 3-Ga, Jung-Gu, Seoul 100-715 (Korea, Republic of); Song, Han-Byul, E-mail: kuackyang@ssu.ac.kr [Department of Chemical Engineering, Soongsil University, Sangdo-Ro 369, Dongjak-Gu, Seoul 156-743 (Korea, Republic of); Kim, Jung-Wk, E-mail: kimjw@snu.ac.kr [Department of Environmental Planning, Graduate School of Environmental Studies, Seoul National University, San 56-1, Sillim-Dong, Gwanak-Gu, Seoul 151-742 (Korea, Republic of); Hwang, Sun-Jin, E-mail: sjhwang@khu.ac.kr [Department of Environmental Science and Engineering, Center for Environmental Studies, Kyung Hee University, Seocheon-Dong, Giheung-Gu, Yongin-Si, Gyeonggi-Do 446-701 (Korea, Republic of)

2011-09-15T23:59:59.000Z

315

Recycling and Disposal of Spent Selective Catalytic Reduction Catalyst  

Science Conference Proceedings (OSTI)

Selective catalytic reduction (SCR) technology has become widespread within the utility industry as a means of controlling emissions of nitrogen oxides (NOx). The technology uses a solid catalyst that deactivates over time; and thus significant volumes of catalyst will need regeneration, recycle, or disposal. This study examined issues related to spent catalyst recycle and disposal.

2003-11-12T23:59:59.000Z

316

Summary - Disposal Practices at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did This Review Disposal operations have been ongoing at the Savannah River Site (SRS) for over 50 years. Active disposal in E-Area, is near the center of the site. Although a wide range of wastes are being managed at the SRS, only low level radioactive wastes (LLRW) are disposed of on site. Wastes are disposed of in unlined slit and engineered trenches, and in low activity waste and intermediate level vaults. Some wastes are isolated in place with grout and all wastes will be covered with a cap that includes a hydraulic barrier to limit precipitation infiltration. The objective of this review was to

317

Low-Level Waste Disposal Facility Federal Review Group Manual  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP MANUAL REVISION 3 JUNE 2008 (This page intentionally left blank) Low-Level JVllsfe Disposal Fllcili~l' Federal Review Group il1allUlli Revision 3, June 200S Concurrence The Low-Level Waste Disposal Facility Federal Review Group Manual, Revision 3, is approved for use as of the most recent date below. Date Chair, Low-Level Waste Disposal Federal Review Group Andrew WalJo, 1II Deputy Director, Otlice of Nuclear Safety, Quality Assurance, and Environment Department of Energy OHlce of Health, Safety, and Security e C. WilJiams Associate Administrator for Infrastructure and Environment National Nuclear Security Administration Low-Level 'Vaste Disposal Facility Federal Review Group J1aJll/ai

318

NNSA Reaches LEU Disposal Milestone | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Reaches LEU Disposal Milestone | National Nuclear Security Reaches LEU Disposal Milestone | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Reaches LEU Disposal Milestone NNSA Reaches LEU Disposal Milestone November 08, 2004 Aiken, SC NNSA Reaches LEU Disposal Milestone The National Nuclear Security Administration's reached an important

319

OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE December 1, 2010 - 12:00pm Addthis OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE Oak Ridge, TN - The Environmental Management Waste Management Facility (EMWMF) provides the onsite disposal capability for the majority of cleanup-generated wastes on the Oak Ridge Reservation. EMWMF has continued a long-standing pattern of safe, complaint operations with 3,000 days without a lost workday case since operations commenced on May 28, 2002. The EMWMF has placed 1.5 million tons of waste and fill in the facility. The EMWMF receives waste from many Oak Ridge cleanup projects, including American Recovery and Reinvestment Act-funded projects, multiple

320

Drilling Waste Management Fact Sheet: Offsite Disposal at Commercial  

NLE Websites -- All DOE Office Websites (Extended Search)

Commercial Disposal Facilities Commercial Disposal Facilities Fact Sheet - Commercial Disposal Facilities Although drilling wastes from many onshore wells are managed at the well site, some wastes cannot be managed onsite. Likewise, some types of offshore drilling wastes cannot be discharged, so they are either injected underground at the platform (not yet common in the United States) or are hauled back to shore for disposal. According to an American Petroleum Institute waste survey, the exploration and production segment of the U.S. oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes in 1985. The report estimates that 28% of drilling wastes are sent to offsite commercial facilities for disposal (Wakim 1987). A similar American Petroleum Institute study conducted ten years later found that the volume of drilling waste had declined substantially to about 150 million bbl.

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Composite analysis E-area vaults and saltstone disposal facilities  

Science Conference Proceedings (OSTI)

This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

Cook, J.R.

1997-09-01T23:59:59.000Z

322

2009 Performance Assessment for the Saltstone Disposal Facility |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Performance Assessment for the Saltstone Disposal Facility Performance Assessment for the Saltstone Disposal Facility 2009 Performance Assessment for the Saltstone Disposal Facility This Performance Assessment (PA) for the Savannah River Site (SRS) was prepared to support the operation and eventual closure of the Saltstone Disposal Facility (SDF). This PA was prepared to demonstrate compliance with the pertinent requirements of the United States Department of Energy (DOE) Order 435.1, Change 1, Radioactive Waste Management, Chapter IV, and Title 10, of the Code of Federal Regulations (CFR) Part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Subpart C as required by the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, Section 3116. [DOE O 435.1-1, 10 CFR 61, NDAA_3116]

323

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal Research and Development Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW) generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made in the U.S and other nations, but gaps in knowledge still exist. This document provides an evaluation and prioritization of R&D opportunities

324

DOE - Office of Legacy Management -- Cheney Disposal Cell - 008  

NLE Websites -- All DOE Office Websites (Extended Search)

Cheney Disposal Cell - 008 Cheney Disposal Cell - 008 FUSRAP Considered Sites Site: Cheney Disposal Cell (008) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: All of the uranium mill tailings and other residual radioactive materials from the former Grand Junction uranium mill site were disposed of in this dedicated disposal cell. The cell is authorized to remain open until 2003 to accept any additional byproduct materials from Title I UMTRA sites and the Monticello, Utah site; e.g. materials from additional vicinity properties that may be identified. The Department of Energy¬Ņs Grand Junction Office is responsible for Long Term Surveillance and Maintenance

325

THE ECONOMICS AND HAZARD POTENTIAL OF WASTE DISPOSAL  

SciTech Connect

The two most important considerations in the disposal of radioactive wastes are safety and economy. All other steps in the waste disposal complex must be tuned to accomplish these two goals. In general, the hazardous waste in the nuclear power complex affect the cost of the nuclear power reactor fuel cycle, the general environment since disposal must exclude radioactivity from the environment for over 500 years, the costs and/or methods of waste treatment including fission product utilization, the methods of shipping, the location of chemical processing plants and waste disposal sites, the methods of disposal best suited for a particular type of waste or site location, and potential public damage and third-party liability.

Arnold, E.D.

1957-07-01T23:59:59.000Z

326

Isotopic dilution of {sup 233}U with depleted uranium for criticality safety in processing and disposal  

SciTech Connect

The disposal of excess {sup 233}U as waste is being considered. Because {sup 233}U is a fissile material, a key requirement for processing {sup 233}U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile {sup 233}U with nonfissile {sup 238}U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of {sup 233}U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % {sup 233}U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO{sub 2}), water (H{sub 2}O), {sup 233}U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % {sup 235}U) are required to dilute 1 part of {sup 233}U to this limit in a water-moderated system with no SiO{sub 2} present. Thus for the U.S. inventory of {sup 233}U, several hundred metric tons of DU would be required for isotopic dilution.

Hopper, C.M.; Wright, R.Q.; Elam, K.R.; Forsberg, C.W.

1997-07-01T23:59:59.000Z

327

Combination gas-producing and waste-water disposal well. [DOE patent application  

DOE Patents (OSTI)

The present invention is directed to a waste-water disposal system for use in a gas recovery well penetrating a subterranean water-containing and methane gas-bearing coal formation. A cased bore hole penetrates the coal formation and extends downwardly therefrom into a further earth formation which has sufficient permeability to absorb the waste water entering the borehole from the coal formation. Pump means are disposed in the casing below the coal formation for pumping the water through a main conduit towards the water-absorbing earth formation. A barrier or water plug is disposed about the main conduit to prevent water flow through the casing except for through the main conduit. Bypass conduits disposed above the barrier communicate with the main conduit to provide an unpumped flow of water to the water-absorbing earth formation. One-way valves are in the main conduit and in the bypass conduits to provide flow of water therethrough only in the direction towards the water-absorbing earth formation.

Malinchak, R.M.

1981-09-03T23:59:59.000Z

328

Disposal of defense spent fuel and HLW from the Idaho Chemical Processing Plant  

SciTech Connect

Acid high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage ate the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal.

Ermold, L.F.; Loo, H.H.; Klingler, R.D.; Herzog, J.D.; Knecht, D.A.

1992-12-01T23:59:59.000Z

329

On-Site Disposal Facility Inspection Report  

Office of Legacy Management (LM)

8947.1 8947.1 09/13 On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 09/13 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 09/13 North Face Cell 1 North Drainage (looking west) 6319D-6206 6319D-6205 8947.4 09/13 East Face Cell 2 West Face Cell 2 6319D-6230 6319D-6209 8947.5 09/13 East Face Cell 3 West Face Cell 3 6319D-6229 6319D-6210 8947.6 09/13 East Face Cell 4 West Face Cell 4 6319D-6227 6319D-62111 8947.7 09/13 East Face Cell 5 West Face Cell 5 6319D-6226 6319D-6213 8947.8 09/13 East Face Cell 6 6319D-6214 6319D-6225 West Face Cell 6 8947.9 09/13 East Face Cell 7 6319D-6215 6319D-6223 West Face Cell 7 8947.10 09/13 East Face Cell 8 6319D-6217 6319D-6220 West Face Cell 8 8947.11 09/13 South Face Cell 8 6319D-6219 6319D-6218 South Drainage (looking west) 8947.12 09/13

330

Disposal of Rocky Flats residues as waste  

SciTech Connect

Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

Dustin, D.F.; Sendelweck, V.S. [EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant; Rivera, M.A. [Lamb Associates, Inc., Rockville, MD (United States)

1993-03-01T23:59:59.000Z

331

Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities  

SciTech Connect

This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility.

Cook, J.R.

2000-03-13T23:59:59.000Z

332

Options and cost for disposal of NORM waste.  

Science Conference Proceedings (OSTI)

Oil field waste containing naturally occurring radioactive material (NORM) is presently disposed of both on the lease site and at off-site commercial disposal facilities. The majority of NORM waste is disposed of through underground injection, most of which presently takes place at a commercial injection facility located in eastern Texas. Several companies offer the service of coming to an operator's site, grinding the NORM waste into a fine particle size, slurrying the waste, and injecting it into the operator's own disposal well. One company is developing a process whereby the radionuclides are dissolved out of the NORM wastes, leaving a nonhazardous oil field waste and a contaminated liquid stream that is injected into the operator's own injection well. Smaller quantities of NORM are disposed of through burial in landfills, encapsulation inside the casing of wells that are being plugged and abandoned, or land spreading. It is difficult to quantify the total cost for disposing of NORM waste. The cost components that must be considered, in addition to the cost of the operation, include analytical costs, transportation costs, container decontamination costs, permitting costs, and long-term liability costs. Current NORM waste disposal costs range from $15/bbl to $420/bbl.

Veil, J. A.

1998-10-22T23:59:59.000Z

333

Use of engineered soils and other site modifications for low-level radioactive waste disposal  

SciTech Connect

The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover.

Not Available

1994-08-01T23:59:59.000Z

334

Immobilized low-level waste disposal options configuration study  

Science Conference Proceedings (OSTI)

This report compiles information that supports the eventual conceptual and definitive design of a disposal facility for immobilized low-level waste. The report includes the results of a joint Westinghouse/Fluor Daniel Inc. evaluation of trade-offs for glass manufacturing and product (waste form) disposal. Though recommendations for the preferred manufacturing and disposal option for low-level waste are outside the scope of this document, relative ranking as applied to facility complexity, safety, remote operation concepts and ease of retrieval are addressed.

Mitchell, D.E.

1995-02-01T23:59:59.000Z

335

Environmental Degradation of Materials in Nuclear Power Systems ...  

Science Conference Proceedings (OSTI)

Environmental Degradation of Materials in Nuclear Power SystemsóWater ... problems associated with spent fuel storage and radioactive waste disposal.

336

Alternative Approaches to Assessing the Performance and Suitability of Yucca Mountain for Spent Fuel Disposal  

Science Conference Proceedings (OSTI)

EPRI's Total System Performance Assessment (TSPA) model has been applied to the candidate spent fuel and high level radioactive waste (HLW) disposal site at Yucca Mountain, Nevada. Building on earlier work, this report details recent modifications to EPRI's TSPA Integrated Multiple Assumptions and Release Code (IMARC), as applied to Yucca Mountain. The report includes performance analyses using IMARC as well as additional analyses and input to provide greater insight. The report also provides recommendat...

1998-12-11T23:59:59.000Z

337

Rules and Regulations for the Disposal of Low-Level Radioactive Waste (Nebraska)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations, promulgated by the Department of Environmental Quality, contain provisions pertaining to the disposal of low-level radioactive waste, disposal facilities, and applicable fees.

338

U.S. Department of Energy Announces the Availability of Disposal...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the Availability of Disposal Contracts for New Nuclear Reactors U.S. Department of Energy Announces the Availability of Disposal Contracts for New Nuclear Reactors October 31, 2008...

339

Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Southwestern Low-Level Radioactive Waste Disposal Compact (South Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) < Back Eligibility Utility Investor-Owned Utility Industrial Construction Municipal/Public Utility Rural Electric Cooperative Fuel Distributor Program Info State South Dakota Program Type Siting and Permitting Provider Southwestern Low-Level Radioactive Waste Commission This legislation authorizes the state's entrance into the Southwestern Low-Level Radioactive Waste Disposal Compact, which provides for the cooperative management of low-level radioactive waste. The Compact is administered by a commission, which can regulate and impose fees on in-state radioactive waste generators. The states of Arizona, California,

340

Depleted Uranium Dioxide as SNF Waste Package Fill: A Disposal...  

NLE Websites -- All DOE Office Websites (Extended Search)

DEPLETED URANIUM DIOXIDE AS SNF WASTE PACKAGE FILL: A DISPOSAL OPTION Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6179 Tel: (865)...

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

DOE - Office of Legacy Management -- Clive Disposal Cell - 036  

Office of Legacy Management (LM)

Survey(s): Site Status: The Clive Disposal Cell is located in Tooele County, Utah. All of the mill tailings and other residual radioactive materials from the South Salt...

342

DOE - Office of Legacy Management -- 11 E (2) Disposal Cell ...  

Office of Legacy Management (LM)

Radiological Survey(s): Site Status: This designation refers to an Envirocare of Utah disposal cell for byproduct material as defined under Section 11 e. (2) of the Atomic...

343

Microsoft Word - WIPP Marks A Decade of Safe Disposal  

NLE Websites -- All DOE Office Websites (Extended Search)

more than 10 years. The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) began disposal operations March 26, 1999 and today serves as an international model...

344

Impacts of Secondary Waste on Near-Surface Disposal Facility ...  

Impacts of Secondary Waste on Near-Surface Disposal Facility at Hanford ... DOE low-level and mixed low-level waste. 1E-06 1E-05 1E-04 1E-03 1E-02 ...

345

A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear safety and security, non-proliferation, and nuclear energy technology we must develop an effective strategy and workable plan for the safe and secure management and disposal of used nuclear fuel and nuclear waste. That is why I asked General Scowcroft and Representative Hamilton to draw on their

346

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

347

Disposing of nuclear waste in a salt bed  

NLE Websites -- All DOE Office Websites (Extended Search)

Disposing of nuclear waste in a salt bed Disposing of nuclear waste in a salt bed 1663 Los Alamos science and technology magazine Latest Issue:November 2013 All Issues ¬Ľ submit Disposing of nuclear waste in a salt bed Decades' worth of transuranic waste from Los Alamos is being laid to rest at the Waste Isolation Pilot Plant in southeastern New Mexico March 25, 2013 Disposing of nuclear waste in a salt bed Depending on the impurities embedded within it, the salt from WIPP can be anything from a reddish, relatively opaque rock to a clear crystal like the one shown here. Ordinary salt effectively seals transuranic waste in a long-term repository Transuranic waste, made of items such as lab coats and equipment that have been contaminated by radioactive elements heavier than uranium, is being shipped from the Los Alamos National Laboratory to a long-term storage

348

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

349

200 Area treated effluent disposal facility operational test report  

Science Conference Proceedings (OSTI)

This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met.

Crane, A.F.

1995-03-01T23:59:59.000Z

350

Waste Disposal Site and Radioactive Waste Management (Iowa)  

Energy.gov (U.S. Department of Energy (DOE))

This section describes the considerations of the Commission in determining whether to approve the establishment and operation of a disposal site for nuclear waste. If a permit is issued, the...

351

Proof of Proper Solid Waste Disposal (West Virginia)  

Energy.gov (U.S. Department of Energy (DOE))

This rule provides guidance to persons occupying a residence or operating a business establishment in this state regarding the approved method of providing proof of proper solid waste disposal to...

352

Minor actinide waste disposal in deep geological boreholes  

E-Print Network (OSTI)

The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. ...

Sizer, Calvin Gregory

2006-01-01T23:59:59.000Z

353

Disposal Facility Reaches 15-Million-Ton Milestone  

Energy.gov (U.S. Department of Energy (DOE))

RICHLAND, Wash. Ė EMís Environmental Restoration Disposal Facility (ERDF) ó a massive landfill for low-level radioactive and hazardous waste at the Hanford site ó has achieved a major cleanup milestone.

354

Canister design for deep borehole disposal of nuclear waste  

E-Print Network (OSTI)

The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories using currently available and proven oil, gas, and geothermal drilling ...

Hoag, Christopher Ian

2006-01-01T23:59:59.000Z

355

Summary - Disposal Practices at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did...

356

Figure ES2. Annual Indices of Real Disposable Income, Vehicle...  

U.S. Energy Information Administration (EIA) Indexed Site

ES2 Figure ES2. Annual Indices of Real Disposable Income, Vehicle-Miles Traveled, Consumer Price Index (CPI-U), and Real Average Retail Gasoline Price, 1978-2004, 1985100...

357

SUPPORTING CALCULATIONS FOR SUBMERGED BED SCRUBBER CONDENSATE DISPOSAL PRECONCEPTUAL STUDY  

Science Conference Proceedings (OSTI)

This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Pre conceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

PAJUNEN AL; TEDESCHI AR

2012-09-18T23:59:59.000Z

358

Second Panel of Disposal Rooms Completed in WIPP Underground  

NLE Websites -- All DOE Office Websites (Extended Search)

Isolation Pilot Plant P.O. Box 3090 Carlsbad, New Mexico 88221 DOENews -2- Underground waste disposal panels are arranged in parallel sets of seven rooms each. Each set of seven...

359

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada EIS-0250: Geologic Repository for the...

360

Draft Environmental Impact Statement for the Disposal of Greater...  

NLE Websites -- All DOE Office Websites (Extended Search)

for the Disposal of Greater-Than-Class C Low-Level Radioactive Waste and GTCC-Like Waste WASHINGTON The Department of Energy (DOE) has issued a Draft Environmental...

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

A microelectronic design for low-cost disposable chemical sensors  

E-Print Network (OSTI)

This thesis demonstrates the novel concept and design of integrated microelectronics for a low-cost disposable chemical sensor. The critical aspects of this chemical sensor are the performance of the microelectronic chip ...

Laval, Stuart S. (Stuart Sean), 1980-

2004-01-01T23:59:59.000Z

362

17.3 - Acquisition, Use and Disposal of Real Property  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Real Estate References DEAR 917.74 - Acquisition, Use, and Disposal of Real Estate DOE Directives DOE Order 413.3B, Program and Project Management for the Acquisition of...

363

Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study  

SciTech Connect

This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Preconceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

Pajunen, A. J.; Tedeschi, A. R.

2012-09-18T23:59:59.000Z

364

Apparatus and methods for supplying auxiliary steam in a combined cycle system  

SciTech Connect

To provide auxiliary steam, a low pressure valve is opened in a combined cycle system to divert low pressure steam from the heat recovery steam generator to a header for supplying steam to a second combined cycle's steam turbine seals, sparging devices and cooling steam for the steam turbine if the steam turbine and gas turbine lie on a common shaft with the generator. Cooling steam is supplied the gas turbine in the combined cycle system from the high pressure steam turbine. Spent gas turbine cooling steam may augment the low pressure steam supplied to the header by opening a high pressure valve whereby high and low pressure steam flows are combined. An attemperator is used to reduce the temperature of the combined steam in response to auxiliary steam flows above a predetermined flow and a steam header temperature above a predetermined temperature. The auxiliary steam may be used to start additional combined cycle units or to provide a host unit with steam turbine cooling and sealing steam during full-speed no-load operation after a load rejection.

Gorman, William G. (Ballston Spa, NY); Carberg, William George (Ballston Spa, NY); Jones, Charles Michael (Ballston Lake, NY)

2002-01-01T23:59:59.000Z

365

CX-010712: Categorical Exclusion Determination  

Energy.gov (U.S. Department of Energy (DOE))

Replace West Hackberry Brine Disposal System Header from MOV-51ís to WHT-14/15 Brine Tanks with HDPE Pipe CX(s) Applied: B5.2 Date: 07/03/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

366

Household waste disposal in Mekelle city, Northern Ethiopia  

SciTech Connect

In many cities of developing countries, such as Mekelle (Ethiopia), waste management is poor and solid wastes are dumped along roadsides and into open areas, endangering health and attracting vermin. The effects of demographic factors, economic and social status, waste and environmental attributes on household solid waste disposal are investigated using data from household survey. Household level data are then analyzed using multinomial logit estimation to determine the factors that affect household waste disposal decision making. Results show that demographic features such as age, education and household size have an insignificant impact over the choice of alternative waste disposal means, whereas the supply of waste facilities significantly affects waste disposal choice. Inadequate supply of waste containers and longer distance to these containers increase the probability of waste dumping in open areas and roadsides relative to the use of communal containers. Higher household income decreases the probability of using open areas and roadsides as waste destinations relative to communal containers. Measures to make the process of waste disposal less costly and ensuring well functioning institutional waste management would improve proper waste disposal.

Tadesse, Tewodros [Agricultural Economics and Rural Policy Group, Wageningen University, Hollandseweg 1 6706 KN Wageningen (Netherlands)], E-mail: tewodroslog@yahoo.com; Ruijs, Arjan [Environmental Economics and Natural Resources Group, Wageningen University, P.O. Box 8130, 6700 EW Wageningen (Netherlands); Hagos, Fitsum [International Water Management Institute (IWMI), Subregional Office for the Nile Basin and East Africa, P.O. Box 5689, Addis Ababa (Ethiopia)

2008-07-01T23:59:59.000Z

367

Assessment of subsurface salt water disposal experience on the Texas and Louisiana Gulf Coast for applications to disposal of salt water from geopressured geothermal wells  

SciTech Connect

A representative cross section of the literature on the disposal of geothermal brine was perused and some of the general information and concepts is summarized. The following sections are included: disposal statistics--Texas Railroad Commission; disposal statistics--Louisiana Office of Conservation; policies for administering salt water disposal operations; salt water disposal experience of Gulf Coast operators; and Federal Strategic Petroleum Reserve Program's brine disposal operations. The literature cited is listed in the appended list of references. Additional literature is listed in the bibliography. (MHR)

Knutson, C.K.; Boardman, C.R.

1978-08-04T23:59:59.000Z

368

Assessment of subsurface salt water disposal experience on the Texas and Louisiana Gulf Coast for applications to disposal of salt water from geopressured geothermal wells  

DOE Green Energy (OSTI)

A representative cross section of the literature on the disposal of geothermal brine was perused and some of the general information and concepts is summarized. The following sections are included: disposal statistics--Texas Railroad Commission; disposal statistics--Louisiana Office of Conservation; policies for administering salt water disposal operations; salt water disposal experience of Gulf Coast operators; and Federal Strategic Petroleum Reserve Program's brine disposal operations. The literature cited is listed in the appended list of references. Additional literature is listed in the bibliography. (MHR)

Knutson, C.K.; Boardman, C.R.

1978-08-04T23:59:59.000Z

369

Summary - Operational Issues at the Environmental Restoration Disposal Facility (ERDF) at Hanford  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ERDF ERDF ETR Report Date: June 2007 ETR-6 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Operational Issues at the Environmental Restoration Disposal Facility(ERDF) at Hanford Why DOE-EM Did This Review The ERDF is a large- scale disposal facility authorized to receive waste from Hanford cleanup activities. It contains double-lined cells with a RCRA Subtitle C- type liner and leachate collection system. By 2007, 6.8 million tons of waste with 39,000 Curies of radioactivity had been placed in the ERDF. In 2006, events occurred that affected the operation of the automatic leachate transfer pumps and a technician confessed to having not performed compaction tests and to falsification of the data.

370

West Hackberry Brine Disposal Project pre-discharge characterization. Final report  

SciTech Connect

The physical, chemical and biological attributes are described for: (1) a coastal marine environment centered about a Department of Energy Strategic Petroleum Reserve (SPR) brine disposal site 11.4 km off the southwest coast of Louisiana; and (2) the lower Calcasieu and Sabine estuarine systems that provide leach waters for the SPR project. A three month sampling effort, February through April 1981, and previous investigations from the study area are integrated to establish baseline information for evaluation of impacts from brine disposal in the nearshore marine waters and from freshwater withdrawal from the coastal marsh of the Chenier Plain. January data are included for some tasks that sampled while testing and mobilizing their instruments prior to the February field effort. The study addresses the areas of physical oceanography, estuarine hydrology and hydrography, water and sediment quality, benthos, nekton, phytoplankton, zooplankton, and data management.

DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C. (eds.) [eds.

1982-01-01T23:59:59.000Z

371

Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility  

Science Conference Proceedings (OSTI)

In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

Alexander, D.J.; Johnson, V.G.

1993-09-01T23:59:59.000Z

372

Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1  

SciTech Connect

This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, admin facility, weigh scale, decon building, treatment systems, and various staging/storage areas. These facilities were designed and are being constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery Act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the central Idaho National Laboratory (INL) facilityyy for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams. This compliance demonstration document discusses the conceptual site model for the ICDF Complex area. Within this conceptual site model, the selection of the area for the ICDF Complex is discussed. Also, the subsurface stratigraphy in the ICDF Complex area is discussed along with the existing contamination beneath the ICDF Complex area. The designs for the various ICDF Complex facilities are also included in this compliance demonstration document. These design discussions are a summary of the design as presented in the Remedial Design/Construction Work Plans for the ICDF landfill and evaporation pond and the Staging, Storage, Sizing, and Treatment Facility. Each of the major facilities or systems is described including the design criteria.

J. Simonds

2006-09-01T23:59:59.000Z

373

Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the various technologies available. It is hoped that the resulting research can build a bridge between technology transfer research and waste disposal research in order to enhance the exchange of more sustainable solutions in future.

Dorn, Thomas, E-mail: thomas.dorn@uni-rostock.de [University of Rostock, Faculty of Agricultural and Environmental Sciences, Department Waste Management, Justus-v.-Liebig-Weg 6, 18059 Rostock (Germany); Nelles, Michael, E-mail: michael.nelles@uni-rostock.de [University of Rostock, Faculty of Agricultural and Environmental Sciences, Department Waste Management, Justus-v.-Liebig-Weg 6, 18059 Rostock (Germany); Flamme, Sabine, E-mail: flamme@fh-muenster.de [University of Applied Sciences Muenster, Corrensstrasse 25, 48149 Muenster (Germany); Jinming, Cai [Hefei University of Technology, 193 Tunxi Road, 230009 Hefei (China)

2012-11-15T23:59:59.000Z

374

NON-SYMMETRICAL MAIN COOLANT SYSTEM ANALYSIS (NOMACS). PART I  

SciTech Connect

Non-symmetrical main coolant system analysis is an IBM-704 digital program for calculating the reactor generation, primary coolant temperature distribution, and steam temperature, pressure, and flow to the main and auxiliary turbines during a transient period. The program represents a system composed of a two-pass high pressure water cooled reactor ivith tivo main primary coolant loops each having its own steam generator, separator, and drum. The generated steam from each loop is piped into a common header which is then piped to the main and auxiliary turbines and other steam loads in the system. The mathematical representation for solution is described. (M.H.R.)

Larsen, R.C.

1957-09-11T23:59:59.000Z

375

Shale disposal of U.S. high-level radioactive waste.  

SciTech Connect

This report evaluates the feasibility of high-level radioactive waste disposal in shale within the United States. The U.S. has many possible clay/shale/argillite basins with positive attributes for permanent disposal. Similar geologic formations have been extensively studied by international programs with largely positive results, over significant ranges of the most important material characteristics including permeability, rheology, and sorptive potential. This report is enabled by the advanced work of the international community to establish functional and operational requirements for disposal of a range of waste forms in shale media. We develop scoping performance analyses, based on the applicable features, events, and processes identified by international investigators, to support a generic conclusion regarding post-closure safety. Requisite assumptions for these analyses include waste characteristics, disposal concepts, and important properties of the geologic formation. We then apply lessons learned from Sandia experience on the Waste Isolation Pilot Project and the Yucca Mountain Project to develop a disposal strategy should a shale repository be considered as an alternative disposal pathway in the U.S. Disposal of high-level radioactive waste in suitable shale formations is attractive because the material is essentially impermeable and self-sealing, conditions are chemically reducing, and sorption tends to prevent radionuclide transport. Vertically and laterally extensive shale and clay formations exist in multiple locations in the contiguous 48 states. Thermal-hydrologic-mechanical calculations indicate that temperatures near emplaced waste packages can be maintained below boiling and will decay to within a few degrees of the ambient temperature within a few decades (or longer depending on the waste form). Construction effects, ventilation, and the thermal pulse will lead to clay dehydration and deformation, confined to an excavation disturbed zone within a few meters of the repository, that can be reasonably characterized. Within a few centuries after waste emplacement, overburden pressures will seal fractures, resaturate the dehydrated zones, and provide a repository setting that strongly limits radionuclide movement to diffusive transport. Coupled hydrogeochemical transport calculations indicate maximum extents of radionuclide transport on the order of tens to hundreds of meters, or less, in a million years. Under the conditions modeled, a shale repository could achieve total containment, with no releases to the environment in undisturbed scenarios. The performance analyses described here are based on the assumption that long-term standards for disposal in clay/shale would be identical in the key aspects, to those prescribed for existing repository programs such as Yucca Mountain. This generic repository evaluation for shale is the first developed in the United States. Previous repository considerations have emphasized salt formations and volcanic rock formations. Much of the experience gained from U.S. repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, is applied here to scoping analyses for a shale repository. A contemporary understanding of clay mineralogy and attendant chemical environments has allowed identification of the appropriate features, events, and processes to be incorporated into the analysis. Advanced multi-physics modeling provides key support for understanding the effects from coupled processes. The results of the assessment show that shale formations provide a technically advanced, scientifically sound disposal option for the U.S.

Sassani, David Carl; Stone, Charles Michael; Hansen, Francis D.; Hardin, Ernest L.; Dewers, Thomas A.; Martinez, Mario J.; Rechard, Robert Paul; Sobolik, Steven Ronald; Freeze, Geoffrey A.; Cygan, Randall Timothy; Gaither, Katherine N.; Holland, John Francis; Brady, Patrick Vane

2010-05-01T23:59:59.000Z

376

Final DUF6 PEIS: Volume 2: Appendix I; Disposal of Oxide  

NLE Websites -- All DOE Office Websites (Extended Search)

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-80 TABLES I.1 Summary of Depleted Uranium Chemical Forms and Disposal Options Considered . . . . . . . . . . . . ....

377

Analysis of environmental regulations governing the disposal of geothermal wastes in California  

DOE Green Energy (OSTI)

Federal and California regulations governing the disposal of sludges and liquid wastes associated with the production of electricity from geothermal resources were evaluated. Current disposal practices, near/far term disposal requirements, and the potential for alternate disposal methods or beneficial uses for these materials were determined. 36 refs., 3 figs., 15 tabs. (ACR)

Royce, B.A.

1985-09-01T23:59:59.000Z

378

Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance  

Energy.gov (U.S. Department of Energy (DOE))

Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance

379

Reactor Vessel Head Disposal Campaign for Nuclear Management Company  

SciTech Connect

After establishing a goal to replace as many reactor vessel heads as possible - in the shortest time and at the lowest cost as possible - Nuclear Management Company (NMC) initiated an ambitious program to replace the heads on all six of its pressurized water reactors. Currently, four heads have been replaced; and four old heads have been disposed of. In 2002, NMC began fabricating the first of its replacement reactor vessel heads for the Kewaunee Nuclear Plant. During its fall 2004 refueling outage, Kewaunee's head was replaced and the old head was prepared for disposal. Kewaunee's disposal project included: - Down-ending, - Draining, - Decontamination, - Packaging, - Removal from containment, - On-Site handling, - Temporary storage, - Transportation, - Disposal. The next two replacements took place in the spring of 2005. Point Beach Nuclear Plant (PBNP) Unit 2 and Prairie Island Nuclear Generating Plant (PINGP) Unit 2 completed their head replacements during their scheduled refueling outages. Since these two outages were scheduled so close to each other, their removal and disposal posed some unique challenges. In addition, changes to the handling and disposal programs were made as a result of lessons learned from Kewaunee. A fourth head replacement took place during PBNP Unit 1's refueling outage during the fall of 2005. A number of additional changes took place. All of these changes and challenges are discussed in the paper. NMC's future schedule includes PINGP Unit 1's installation in Spring 2006 and Palisades' installation during 2007. NMC plans to dispose of these two remaining heads in a similar manner. This paper presents a summary of these activities, plus a discussion of lessons learned. (authors)

Hoelscher, H.L.; Closs, J.W. [Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 (United States); Johnson, S.A. [Duratek, Inc., 140 Stoneridge Drive, Columbia, SC 29210 (United States)

2006-07-01T23:59:59.000Z

380

Gasification combined cycle: Carbon dioxide recovery, transport, and disposal  

SciTech Connect

The objective of the project is to develop engineering evaluations of technologies for the capture, use, and disposal of carbon dioxide (CO{sub 2}). This project emphasizes CO{sub 2}-capture technologies combined with integrated gasification combined-cycle (IGCC) power systems. Complementary evaluations address CO{sub 2} transportation, CO{sub 2} use, and options for the long-term sequestering of unused CO{sub 2}. Commercially available CO{sub 2}-capture technology is providing a performance and economic baseline against which to compare innovative technologies. The intent is to provide the CO{sub 2} budget, or an {open_quotes}equivalent CO{sub 2}{close_quotes} budget, associated with each of the individual energy-cycle steps, in addition to process design capital and operating costs. The value used for the {open_quotes}equivalent CO{sub 2}{close_quotes} budget is 1 kg of CO{sub 2} per kilowatt-hour (electric). The base case is a 458-MW IGCC system that uses an air-blown Kellogg-Rust-Westinghouse agglomerating fluidized-bed gasifier, Illinois No. 6 bituminous coal feed, and in-bed sulfur removal. Mining, feed preparation, and conversion result in a net electric power production of 454 MW, with a CO{sub 2} release rate of 0.835 kg/kWhe. Two additional life-cycle energy balances for emerging technologies were considered: (1) high-temperature CO{sub 2} separation with calcium- or magnesium-based sorbents, and (2) ambient-temperature facilitated-transport polymer membranes for acid-gas removal.

Doctor, R.D.; Molburg, J.C.; Thimmapuram, P.R.; Berry, G.F.; Livengood, C.D.

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Disposal of oil field wastes into salt caverns: Feasibility, legality, risk, and costs  

Science Conference Proceedings (OSTI)

Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of oil field wastes, the risks to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne`s research indicates that disposal of oil field wastes into salt caverns is feasible and legal. The risk from cavern disposal of oil field wastes appears to be below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

Veil, J.A. [Argonne National Lab., Washington, DC (United States). Water Policy Program

1997-10-01T23:59:59.000Z

382

Integrated Disposal Facility FY2011 Glass Testing Summary Report  

SciTech Connect

Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

2011-09-29T23:59:59.000Z

383

Reference design and operations for deep borehole disposal of high-level radioactive waste.  

SciTech Connect

A reference design and operational procedures for the disposal of high-level radioactive waste in deep boreholes have been developed and documented. The design and operations are feasible with currently available technology and meet existing safety and anticipated regulatory requirements. Objectives of the reference design include providing a baseline for more detailed technical analyses of system performance and serving as a basis for comparing design alternatives. Numerous factors suggest that deep borehole disposal of high-level radioactive waste is inherently safe. Several lines of evidence indicate that groundwater at depths of several kilometers in continental crystalline basement rocks has long residence times and low velocity. High salinity fluids have limited potential for vertical flow because of density stratification and prevent colloidal transport of radionuclides. Geochemically reducing conditions in the deep subsurface limit the solubility and enhance the retardation of key radionuclides. A non-technical advantage that the deep borehole concept may offer over a repository concept is that of facilitating incremental construction and loading at multiple perhaps regional locations. The disposal borehole would be drilled to a depth of 5,000 m using a telescoping design and would be logged and tested prior to waste emplacement. Waste canisters would be constructed of carbon steel, sealed by welds, and connected into canister strings with high-strength connections. Waste canister strings of about 200 m length would be emplaced in the lower 2,000 m of the fully cased borehole and be separated by bridge and cement plugs. Sealing of the upper part of the borehole would be done with a series of compacted bentonite seals, cement plugs, cement seals, cement plus crushed rock backfill, and bridge plugs. Elements of the reference design meet technical requirements defined in the study. Testing and operational safety assurance requirements are also defined. Overall, the results of the reference design development and the cost analysis support the technical feasibility of the deep borehole disposal concept for high-level radioactive waste.

Herrick, Courtney Grant; Brady, Patrick Vane; Pye, Steven; Arnold, Bill Walter; Finger, John Travis; Bauer, Stephen J.

2011-10-01T23:59:59.000Z

384

EM's Richland Operations Office Celebrates Disposal Achievement in 2013 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM's Richland Operations Office Celebrates Disposal Achievement EM's Richland Operations Office Celebrates Disposal Achievement in 2013 EM's Richland Operations Office Celebrates Disposal Achievement in 2013 December 24, 2013 - 12:00pm Addthis Workers sample a well used to monitor groundwater at the Hanford site. Workers sample a well used to monitor groundwater at the Hanford site. Workers separate a glove box for removal from Hanford√ʬĬôs Plutonium Finishing Plant. Workers separate a glove box for removal from Hanford's Plutonium Finishing Plant. Workers sample a well used to monitor groundwater at the Hanford site. Workers separate a glove box for removal from Hanford's Plutonium Finishing Plant. RICHLAND, Wash. - EM's Richland Operations Office's 2013 accomplishments ranged from cleaning up buildings and waste sites to treating a record

385

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars August 1, 2012 - 12:00pm Addthis For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory√ʬĬôs (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation√ʬĬôs few repositories for U-233 and other special nuclear materials dating back to the Manhattan Project. For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory's (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation's few repositories for U-233 and other special nuclear materials

386

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars August 1, 2012 - 12:00pm Addthis For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory√ʬĬôs (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation√ʬĬôs few repositories for U-233 and other special nuclear materials dating back to the Manhattan Project. For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory's (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation's few repositories for U-233 and other special nuclear materials

387

Laboratory to demolish excavation enclosures at Material Disposal Area B  

NLE Websites -- All DOE Office Websites (Extended Search)

Excavation Enclosures At MDA B Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Communications Office (505) 667-7000 "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

388

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

00: Managing Treatment, Storage, and Disposal of Radioactive 00: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY This EIS evaluates the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008 EIS-0200: Amendment to the Record of Decision Treatment and Storage of Transuranic Waste

389

Laboratory to demolish excavation enclosures at Material Disposal Area B  

NLE Websites -- All DOE Office Websites (Extended Search)

Excavation enclosures at MDA B Excavation enclosures at MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Colleen Curran Communications Office (505) 664-0344 Email "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

390

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY Final Waste Management Programmatic Environmental Impact Statement examines the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008

391

Laboratory to demolish excavation enclosures at Material Disposal Area B  

NLE Websites -- All DOE Office Websites (Extended Search)

Excavation Enclosures At MDA B Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Communications Office (505) 667-7000 "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

392

Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Gas, Heat, Water, Sewerage Collection and Disposal, and Street Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) < Back Eligibility Agricultural Commercial Construction Industrial Installer/Contractor Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State South Carolina Program Type Generating Facility Rate-Making Siting and Permitting Provider South Carolina Public Service Commission This legislation applies to public utilities and entities furnishing natural gas, heat, water, sewerage, and street railway services to the public. The legislation addresses rates and services, exemptions, investigations, and records. Article 4 (58-5-400 et seq.) of this

393

Earth melter and method of disposing of feed materials  

DOE Patents (OSTI)

An apparatus, and method of operating the apparatus is described, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials. 3 figs.

Chapman, C.C.

1994-10-11T23:59:59.000Z

394

Earth melter and method of disposing of feed materials  

DOE Patents (OSTI)

An apparatus, and method of operating the apparatus, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials.

Chapman, Christopher C. (Richland, WA)

1994-01-01T23:59:59.000Z

395

Crystalline ceramics: Waste forms for the disposal of weapons plutonium  

Science Conference Proceedings (OSTI)

At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ``logs``; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium.

Ewing, R.C.; Lutze, W. [New Mexico Univ., Albuquerque, NM (United States); Weber, W.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-05-01T23:59:59.000Z

396

US Recovery Act Smart Grid Projects - Electric Distributions Systems | Open  

Open Energy Info (EERE)

Distributions Systems Distributions Systems Jump to: navigation, search CSV Loading map... {"format":"googlemaps3","type":"ROADMAP","types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"limit":500,"offset":0,"link":"all","sort":[""],"order":[],"headers":"show","mainlabel":"","intro":"","outro":"","searchlabel":"\u2026 further results","default":"","geoservice":"google","zoom":false,"width":"600px","height":"350px","centre":false,"layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","icon":"","visitedicon":"","forceshow":true,"showtitle":true,"hidenamespace":false,"template":false,"title":"","label":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"locations":[{"text":"

397

US Recovery Act Smart Grid Projects - Customer Systems | Open Energy  

Open Energy Info (EERE)

Systems Systems Jump to: navigation, search CSV Loading map... {"format":"googlemaps3","type":"ROADMAP","types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"limit":500,"offset":0,"link":"all","sort":[""],"order":[],"headers":"show","mainlabel":"","intro":"","outro":"","searchlabel":"\u2026 further results","default":"","geoservice":"google","zoom":false,"width":"600px","height":"350px","centre":false,"layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","icon":"","visitedicon":"","forceshow":true,"showtitle":true,"hidenamespace":false,"template":false,"title":"","label":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"locations":[{"text":"

398

US Recovery Act Smart Grid Projects - Integrated and Crosscutting Systems |  

Open Energy Info (EERE)

- Integrated and Crosscutting Systems - Integrated and Crosscutting Systems Jump to: navigation, search CSV Loading map... {"format":"googlemaps3","type":"ROADMAP","types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"limit":500,"offset":0,"link":"all","sort":[""],"order":[],"headers":"show","mainlabel":"","intro":"","outro":"","searchlabel":"\u2026 further results","default":"","geoservice":"google","zoom":false,"width":"600px","height":"350px","centre":false,"layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","icon":"","visitedicon":"","forceshow":true,"showtitle":true,"hidenamespace":false,"template":false,"title":"","label":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"locations":[{"text":"

399

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria  

SciTech Connect

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

W. Mahlon Heileson

2006-10-01T23:59:59.000Z

400

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-4 i (and ii) DRAFT XX-XX-XX LLW Maintenance Guide Revision 0, XX-XX-XX Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3.1 Objectives . . . . . . . . . . . . . . . . . . . . . . . . .

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
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401

Simulation of waste processing, transportation, and disposal operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years. 1

Janis Trone

2000-01-01T23:59:59.000Z

402

Simulation Of Waste Processing, Transportation, And Disposal Operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years.

J. A. Joines; R. R. Barton; K. Kang; P. A. Fishwick; Janis Trone; Angela Guerin

2000-01-01T23:59:59.000Z

403

Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Annual Site Inspection and Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites November 2012 LMS/S09415 ENERGY Legacy Management U.S. DEPARTMENT OF Sherwood, Washington, Disposal Site, 2012 Sherwood, Washington, Disposal Site, 2012 L-Bar, New Mexico, Disposal Site, 2012 L-Bar, New Mexico, Disposal Site, 2012 Bluewater, New Mexico, Disposal Site, 2012 Bluewater, New Mexico, Disposal Site, 2012 Maybell West, Colorado, Disposal Site, 2012 Maybell West, Colorado, Disposal Site, 2012 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy,

404

Improved vortex reactor system  

DOE Patents (OSTI)

An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

1995-01-01T23:59:59.000Z

405

Norfolk Southern boxcar blocking/bracing plan for the mixed waste disposal initiative project. Environmental Restoration Program  

Science Conference Proceedings (OSTI)

The US Department of Energy`s (DOE) Environmental Restoration and Waste Management programs will dispose of mixed waste no longer deemed useful. This project is one of the initial activities used to help meet this goal. The project will transport the {approximately}46,000 drums of existing stabilized mixed waste located at the Oak Ridge K-25 Site and presently stored in the K-31 and K-33 buildings to an off-site commercially licensed and permitted mixed waste disposal facility. Shipping and disposal of all {approximately}46,000 pond waste drums ({approximately}1,000,000 ft{sup 3} or 55,000 tons) is scheduled to occur over a period of {approximately}5--10 years. The first shipment of stabilized pond waste should transpire some time during the second quarter of FY 1994. Martin Marietta Energy Systems, Inc., proposes to line each of the Norfolk Southem boxcars with a prefabricated, white, 15-mm low-density polyethylene (LDPE) liner material. To avoid damaging the bottom of the polyethylene floor liner, a minimum .5 in. plywood will be nailed to the boxcars` nailable metal floor. At the end of the Mixed Waste Disposal Initiative (MWDI) Project workers at the Envirocare facility will dismantle and dispose of all the polyethylene liner and plywood materials. Envirocare of Utah, Inc., located in Clive, Utah, will perform a health physic survey and chemically and radiologically decontaminate, if necessary, each of the rail boxcars prior to them being released back to Energy Systems. Energy Systems will also perform a health physic survey and chemically and radiologically decontaminate, if necessary, each of the rail boxcars prior to them being released back to Norfolk Southem Railroad.

Seigler, R.S.

1994-01-01T23:59:59.000Z

406

From Basic Control to Optimized Systems-Applying Digital Control Systems to Steam Boilers  

E-Print Network (OSTI)

This presentation examines the application of Distributed Digital Controls in order to review the application of this recent control technology towards Steam Boilers in a step-by-step manner. The main purpose of a steam generating boiler is to supply enough steam to meet process demands. Steam conditions must remain as stable as possible, because variations in the steam system can affect downstream processes. Pressure variations in the steam supply header, for example, can have a severe effect on heat transferred to a process. If that process suffers an upset, unstable conditions can propagate from one process to another via the steam supply system. The closer the tolerance in the boiler control system, the smaller the steam header disturbances will be. This reduces the interaction, or 'coupling', of upsets between steam-consuming processes. Also, it may reduce the complexity of instrumentation needed for those processes. If the boiler control system can eliminate major upsets, the downstream processes won't need exotic schemes to compensate for such upsets.

Hockenbury, W. D.

1982-01-01T23:59:59.000Z

407

Success in managing waste with no identified path to disposal at the INEEL  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is aggressively managing waste with no identified path to disposal (WNPD), which was previously termed special case waste (SCW). As a result of several years of this aggressive management, the INEEL has reduced its WNPD volume from approximately 38,000 m{sup 3} in 1993 to approximately 6.33 m{sup 3} in 1999. This paper discusses how the INEEL reduced its WNPD volume. It specifically discusses the beryllium reflector waste produced from the Advanced Test Reactor (ATR) as an example of the INEEL's success in managing its WNPD. The INEEL's success in reducing its WNPD volume is the result of establishing long-range strategic objectives and consistently allocating an annual budget to implement specific work tasks that are consistent with these objectives. In addition, specific short- and long-range work tasks were developed and documented in work control documents. The work tasks are evaluated annually for consistency with the strategic objectives. Since the INEEL has successfully reduced its WNPD volume, it is now focusing on disposing of the remaining volume and preventing future generation of WNPD. As a result of this focused effort, a life-cycle disposal plan was developed for the Advanced Test Reactor (ATR) beryllium waste. This plan covers beryllium reflectors currently stored in the ATR canal and beryllium reflectors generated through 2050. This plan includes a pollution prevention (P2) opportunity, which applies to the DOE complex reactor beryllium reflector waste stream. The P2 opportunity also contributes to planning for the international nuclear industry to extend the life and reduce the radionuclide activation of nonfuel material in existing and newly developed test reactor nuclear power systems. In Fiscal Year 2000, the INEEL is focusing on further reducing its WNPD volume. To completely dispose of the INEEL WNPD, it will need a national plan for disposing of some WNPD categories. Therefore, the INEEL WNPD Program is participating in the DOE complex integrated planning process for legacy and future generated WNPD waste.

C. K. Mullen; M. L. Carboneau; M. R. Leavitt

2000-02-27T23:59:59.000Z

408

Success in Managing Waste With No Identified Path to Disposal at the INEEL  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is aggressively managing waste with no identified path to disposal (WNPD), which was previously termed special case waste (SCW). As a result of several years of this aggressive management, the INEEL has reduced its WNPD volume from approximately 38,000 m3 in 1993 to approximately 6.33 m3 in 1999. This paper discusses how the INEEL reduced its WNPD volume. It specifically discusses the beryllium reflector waste produced from the Advanced Test Reactor (ATR) as an example of the INEEL's success in managing its WNPD. The INEEL's success in reducing its WNPD volume is the result of establishing long-range strategic objectives and consistently allocating an annual budget to implement specific work tasks that are consistent with these objectives. In addition, specific short- and long-range work tasks were developed and documented in work control documents. The work tasks are evaluated annually for consistency with the strategic objectives. Since the INEEL has successfully reduced its WNPD volume, it is now focusing on disposing of the remaining volume and preventing future generation of WNPD. As a result of this focused effort, a life-cycle disposal plan was developed for the Advanced Test Reactor (ATR) beryllium waste. This plan covers beryllium reflectors currently stored in the ATR canal and beryllium reflectors generated through 2050. This plan includes a pollution prevention (P2) opportunity, which applies to the DOE complex reactor beryllium reflector waste stream. The P2 opportunity also contributes to planning for the international nuclear industry to extend the life and reduce the radionuclide activation of nonfuel material in existing and newly developed test reactor nuclear power systems. In Fiscal Year 2000, the INEEL is focusing on further reducing its WNPD volume. To completely dispose of the INEEL WNPD, it will need a national plan for disposing of some WNPD categories. Therefore, the INEEL WNPD Program is participating in the DOE complex integrated planning process for legacy and future generated WNPD waste.

Mullen, Carlan K; Carboneau, Michael Leonard; Leavitt, Max Russell

2000-03-01T23:59:59.000Z

409

INADVERTENT INTRUDER ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY  

SciTech Connect

An On-Site Alternative is being evaluated as part of the Remedial Investigation and Feasibility Study (RI/FS) process for evaluation of alternatives for the disposal of waste generated from decontamination and decommissioning (D&D) at Portsmouth. The On-Site Alternative involves construction of an On-Site Waste Disposal Facility (OSWDF). An inadvertent intruder analysis must be conducted for the OSWDF. The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Therefore, after active institutional control ceases, certain exposure scenarios are assumed to be precluded only by the physical state of the disposal facility, i.e., the integrity of the engineered barriers used in facility construction or the thickness of clean material above the waste. Passive institutional controls, such as permanent marker systems at the disposal site and public records of prior land use, also could prevent inadvertent intrusion after active institutional control ceases, but the efficacy of passive institutional controls is not assumed in this analysis. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr.

Smith, F.; Phifer, M.

2013-09-30T23:59:59.000Z

410

Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it 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 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2010-10-01T23:59:59.000Z

411

Towards a Profitable Means of Municipal Refuse Disposal  

E-Print Network (OSTI)

the process to function profitably despite chemical kinetic uncertainties. Further work is recommended to take not been applied to refuse disposal, although the Chemical Abstracts list many applications, the reaction being: yeast C6 H1206 .2C2 HsOH + 2 C02 Sugars Ethanol The kinetics of cellulose hydrolysis

Columbia University

412

200 Area treated effluent disposal facility operational test specification  

Science Conference Proceedings (OSTI)

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met.

Crane, A.F.

1995-01-12T23:59:59.000Z

413

200 Area treated effluent disposal facility operational test specification  

Science Conference Proceedings (OSTI)

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met.

Crane, A.F.

1995-02-02T23:59:59.000Z

414

8-Waste treatment and disposal A. Responsibility for waste management  

E-Print Network (OSTI)

8- Waste treatment and disposal A. Responsibility for waste management 1. Each worker is responsible for correctly bagging and labeling his/her own waste. 2. A BSL3 technician will be responsible for transporting and autoclaving the waste. Waste will be autoclaved once or twice per day, depending on use

415

Storage and disposal of radioactive waste as glass in canisters  

SciTech Connect

A review of the use of waste glass for the immobilization of high-level radioactive waste glass is presented. Typical properties of the canisters used to contain the glass, and the waste glass, are described. Those properties are used to project the stability of canisterized waste glass through interim storage, transportation, and geologic disposal.

Mendel, J.E.

1978-12-01T23:59:59.000Z

416

Some aspects of low-level radioactive-waste disposal in the US  

Science Conference Proceedings (OSTI)

This report summarizes the NRC supported Shallow Land Burial research program at Brookhaven National Laboraotry and its relationship to the proposed revised ruling on disposal of low level radioactive waste, 10 CFR Part 61. Section of the proposed regulation, which establish the new low level waste classification system and the performance objective placed on waste form, are described briefly. The report also summarizes the preliminary results obtained from the EPA program in which low level waste drums were retrieved from the Atlantic and Pacific Oceans.

Schweitzer, D.G.; Davis, R.E.

1982-01-01T23:59:59.000Z

417

Models for estimation of service life of concrete barriers in low-level radioactive waste disposal  

SciTech Connect

Concrete barriers will be used as intimate parts of systems for isolation of low level radioactive wastes subsequent to disposal. This work reviews mathematical models for estimating the degradation rate of concrete in typical service environments. The models considered cover sulfate attack, reinforcement corrosion, calcium hydroxide leaching, carbonation, freeze/thaw, and cracking. Additionally, fluid flow, mass transport, and geochemical properties of concrete are briefly reviewed. Example calculations included illustrate the types of predictions expected of the models. 79 refs., 24 figs., 6 tabs.

Walton, J.C.; Plansky, L.E.; Smith, R.W. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-09-01T23:59:59.000Z

418

Summary of meeting on disposal of LET&D HEPA filters  

Science Conference Proceedings (OSTI)

This report is a compilation of correspondence between Westinghouse Idaho Nuclear Company and the US EPA over a period of time from 1988 to 1992 (most from 1991-92) regarding waste management compliance with EPA regulations. Typical subjects include: compliance with satellite accumulation requirements; usage of ``Sure Shot`` containers in place of aerosol cans; notice of upcoming recyclable battery shipments; disposition of batteries; HEPA filter leach sampling and permit impacts; functional and operation requirements for the spent filter handling system; summary of meeting on disposal of LET and D HEPA filters; solvent substitution database report; and mercury vapor light analytical testing.

Not Available

1991-11-21T23:59:59.000Z

419

Update on cavern disposal of NORM-contaminated oil field wastes.  

Science Conference Proceedings (OSTI)

Some types of oil and gas production and processing wastes contain naturally occurring radioactive material (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. Argonne National Laboratory has previously evaluated the feasibility, legality, risk and economics of disposing of nonhazardous oil field wastes, other than NORM waste, in salt caverns. Cavern disposal of nonhazardous oil field waste, other than NORM waste, is occurring at four Texas facilities, in several Canadian facilities, and reportedly in Europe. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns as well. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, a review of federal regulations and regulations from several states indicated that there are no outright prohibitions against NORM disposal in salt caverns or other Class II wells, except for Louisiana which prohibits disposal of radioactive wastes or other radioactive materials in salt domes. Currently, however, only Texas and New Mexico are working on disposal cavern regulations, and no states have issued permits to allow cavern disposal of NORM waste. On the basis of the costs currently charged for cavern disposal of nonhazardous oil field waste (NOW), NORM waste disposal in caverns is likely to be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

Veil, J. A.

1998-09-22T23:59:59.000Z

420

Passive containment cooling system  

DOE Patents (OSTI)

A passive containment cooling system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and a gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel and is vented to the drywell. An isolation pool is disposed above the GDCS pool and includes an isolation condenser therein. The condenser has an inlet line disposed in flow communication with the drywell for receiving the non-condensable gas along with any steam released therein following a loss-of-coolant accident (LOCA). The condenser also has an outlet line disposed in flow communication with the drywell for returning to the drywell both liquid condensate produced upon cooling of the steam and the non-condensable gas for reducing pressure within the containment vessel following the LOCA.

Billig, Paul F. (San Jose, CA); Cooke, Franklin E. (San Jose, CA); Fitch, James R. (San Jose, CA)

1994-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Passive containment cooling system  

DOE Patents (OSTI)

A passive containment cooling system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and a gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel and is vented to the drywell. An isolation pool is disposed above the GDCS pool and includes an isolation condenser therein. The condenser has an inlet line disposed in flow communication with the drywell for receiving the non-condensable gas along with any steam released therein following a loss-of-coolant accident (LOCA). The condenser also has an outlet line disposed in flow communication with the drywell for returning to the drywell both liquid condensate produced upon cooling of the steam and the non-condensable gas for reducing pressure within the containment vessel following the LOCA. 1 figure.

Billig, P.F.; Cooke, F.E.; Fitch, J.R.

1994-01-25T23:59:59.000Z

422

Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Preliminary Report on Dual-Purpose Canister Disposal Alternatives Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel (SNF) in existing dual-purpose canisters (DPCs) and other types of storage casks. The first phase includes a set of preliminary disposal concepts and associated technical analyses, identification of additional R&D needs, and a recommendation to proceed with the next phase of the evaluation effort. Preliminary analyses indicate that DPC direct disposal could be technically feasible, at least for certain disposal concepts. DPC disposal concepts include the salt concept, and emplacement

423

NNSS Waste Disposal Proves Vital Resource for DOE Complex | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex March 20, 2013 - 12:00pm Addthis The Area 5 Radioactive Waste Management Site The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels.

424

FAQ 35-What are the potential health risks from disposal of depleted...  

NLE Websites -- All DOE Office Websites (Extended Search)

health risks from disposal of depleted uranium as an oxide? Once depleted uranium has been converted from UF6 to the oxide form, the risk associated with handling at a disposal...

425

Standard Contract for Disposal of SNF and/or HRW | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

for Disposal of SNF andor HRW Standard Contract for Disposal of SNF andor HRW The following document is a contract between the United States of America, represented by the U.S....

426

Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans  

Energy.gov (U.S. Department of Energy (DOE))

Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans

427

Interface control document between PUREX Plant Transition and Solid Waste Disposal Division  

SciTech Connect

The interfacing responsibilities regarding solid waste management are described for the Solid Waste Disposal Division and the PUREX Transition Organization.

Carlson, A.B.

1995-09-01T23:59:59.000Z

428

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

429

Fluid Dynamics of Carbon Dioxide Disposal into Saline Aquifers  

SciTech Connect

Injection of carbon dioxide (CO{sub 2}) into saline aquifers has been proposed as a means to reduce greenhouse gas emissions (geological carbon sequestration). Large-scale injection of CO{sub 2} will induce a variety of coupled physical and chemical processes, including multiphase fluid flow, fluid pressurization and changes in effective stress, solute transport, and chemical reactions between fluids and formation minerals. This work addresses some of these issues with special emphasis given to the physics of fluid flow in brine formations. An investigation of the thermophysical properties of pure carbon dioxide, water and aqueous solutions of CO{sub 2} and NaCl has been conducted. As a result, accurate representations and models for predicting the overall thermophysical behavior of the system CO{sub 2}-H{sub 2}O-NaCl are proposed and incorporated into the numerical simulator TOUGH2/ECO{sub 2}. The basic problem of CO{sub 2} injection into a radially symmetric brine aquifer is used to validate the results of TOUGH2/ECO2. The numerical simulator has been applied to more complex flow problem including the CO{sub 2} injection project at the Sleipner Vest Field in the Norwegian sector of the North Sea and the evaluation of fluid flow dynamics effects of CO{sub 2} injection into aquifers. Numerical simulation results show that the transport at Sleipner is dominated by buoyancy effects and that shale layers control vertical migration of CO{sub 2}. These results are in good qualitative agreement with time lapse surveys performed at the site. High-resolution numerical simulation experiments have been conducted to study the onset of instabilities (viscous fingering) during injection of CO{sub 2} into saline aquifers. The injection process can be classified as immiscible displacement of an aqueous phase by a less dense and less viscous gas phase. Under disposal conditions (supercritical CO{sub 2}) the viscosity of carbon dioxide can be less than the viscosity of the aqueous phase by a factor of 15. Because of the lower viscosity, the CO{sub 2} displacement front will have a tendency towards instability. Preliminary simulation results show good agreement between classical instability solutions and numerical predictions of finger growth and spacing obtained using different gas/liquid viscosity ratios, relative permeability and capillary pressure models. Further studies are recommended to validate these results over a broader range of conditions.

Garcia, Julio Enrique

2003-12-18T23:59:59.000Z

430

The WIPP is the nation's first geologic facility designed for permanent disposal of transuranic  

E-Print Network (OSTI)

The WIPP is the nation's first geologic facility designed for permanent disposal of transuranic, New Mexico to dispose of this waste. The TRU waste being disposed at the WIPP is packaged into drums-level waste and spent nuclear fuel. The WIPP has a total capacity of 6.2 million cubic feet of TRU waste

431

River Protection Project (RPP) Tank Waste Retrieval and Disposal Mission Technical Baseline Summary Description  

Science Conference Proceedings (OSTI)

This document is one of the several documents prepared by Lockheed Martin Hanford Corp. to support the U. S. Department of Energy's Tank Waste Retrieval and Disposal mission at Hanford. The Tank Waste Retrieval and Disposal mission includes the programs necessary to support tank waste retrieval; waste feed, delivery, storage, and disposal of immobilized waste; and closure of the tank farms.

DOVALLE, O.R.

1999-12-29T23:59:59.000Z

432

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste  

E-Print Network (OSTI)

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste Batteries, used or unwanted including lithium, alkaline, lead ­ acid or lithium aluminum hydride Chemical Waste Check Disposal of Toxics website for disposal options or Take to Bookstore Biological Waste Biological Waste Residential

Zaferatos, Nicholas C.

433

Quantifying Deep Vadose Zone Soil Water Potential Changes At A Waste Disposal Site  

Science Conference Proceedings (OSTI)

Recent advances in moisture monitoring using tensiometers has allowed long-duration, high quality data sets from within the deep vadose zone. A network of about 30 advanced tensiometers in 18 wells provided field-scale data to monitor moisture conditions and movement in the subsurface in and around a mixed waste disposal site at depths ranging from 6 to over 67 m below land surface (bls). Sensors are located in both sediments and fractured rock within the geologic profile and some have been in operation for over 10 years. The moisture monitoring was able to detect long term declines in moisture content presumably in response to lower than normal precipitation and resultant infiltration over the time period from 2000 to 2004. This trend was reversed in 2005 and 2006 in more than half of the monitoring sites over the 6 to 33 m depth interval and in several monitoring sites from 33 to 67 m, in response to normal to above normal precipitation. This tensiometer data can be used to evaluate the appropriateness of the current conceptual model of flow at this site. It also shows that a moisture monitoring system should be effective to rapidly validate that a proposed remedial action (such as placement of an ET cover) would be effective in reducing the moisture movement to levels similar to those in undisturbed sites outside of the disposal area. This paper will describe the instrument design, how the instruments were installed, and the resultant data from this monitoring system.

Joel M. Hubbell; Deborah L. McElroy

2007-10-01T23:59:59.000Z

434

Readiness plan, Hanford 300 Area Treated Effluent Disposal Facility: Revision 1  

Science Conference Proceedings (OSTI)

The 300 Area Treated Effluent Disposal Facility (TEDF) is designed for the collection, treatment, and eventual disposal of liquid waste from the 300 Area Process Sewer (PS) system. The PS currently discharges water to the 300 Area Process Trenches. Facilities supported total 54 buildings, including site laboratories, inactive buildings, and support facilities. Effluent discharges to the process sewer from within these facilities include heating, ventilation, and air conditioning systems, heat exchangers, floor drains, sinks, and process equipment. The wastewaters go through treatment processes that include iron coprecipitation, ion exchange and ultraviolet oxidation. The iron coprecipitation process is designed to remove general heavy metals. A series of gravity filters then complete the clarification process by removing suspended solids. Following the iron coprecipitation process is the ion exchange process, where a specific resin is utilized for the removal of mercury. The final main unit operation is the ultraviolet destruction process, which uses high power ultraviolet light and hydrogen peroxide to destroy organic molecules. The objective of this readiness plan is to provide the method by which line management will prepare for a Readiness Assessment (RA) of the TEDF. The self-assessment and RA will assess safety, health, environmental compliance and management readiness of the TEDF. This assessment will provide assurances to both WHC and DOE that the facility is ready to start-up and begin operation.

Storm, S.J.

1994-11-08T23:59:59.000Z

435

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

436

WIPP Reaches Milestone ¬Ą First Disposal Room Filled  

NLE Websites -- All DOE Office Websites (Extended Search)

WIPP Reaches Milestone - First Disposal Room Filled CARLSBAD, N.M., September 4, 2001 - The U.S. Department of Energy's (DOE) Carlsbad Field Office today announced that Room 7 of Panel 1 at the Waste Isolation Pilot Plant (WIPP), the first underground room used for disposal operations, has been filled to capacity with transuranic waste. The milestone was reached at about 3:30 p.m. on August 24, as Waste Handling personnel emplaced a shipment of waste from the Idaho National Engineering and Environmental Laboratory. On August 25, Underground Operations personnel completed installation of a chain link mesh barrier and cloth drape across the entrance to the room to officially declare the area "closed." The first shipment of waste, which came

437

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NDAA Section NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Section 3116 is currently only applicable to Idaho National Laboratory (INL) and the Savannah River Site (SRS). The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste)

438

The Effects of CO2 Disposal on Marine Nitrification Processes  

NLE Websites -- All DOE Office Websites (Extended Search)

Effects of CO Effects of CO 2 Disposal on Marine Nitrification Processes Michael H. Huesemann (michael.huesemann@pnl.gov, 360-681-3618) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Ann D. Skillman (ann.skillman@pnl.gov, 360-681-3649) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Eric A. Crecelius (eric.crecelius@pnl.gov, 360-681-3604) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Abstract In an attempt to reduce the threat of global warming, it has been proposed that the rise of atmospheric carbon dioxide concentrations be reduced by the ocean disposal of CO 2 from the flue gases of fossil fuel-fired power plants. The release of large amounts of

439

LANL demolishes first containment dome at disposal area  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL Demolishes First Containment Dome LANL Demolishes First Containment Dome LANL demolishes first containment dome at disposal area It once housed thousands of drums of radioactive waste that have been shipped to the Waste Isolation Pilot Plant for disposal. September 30, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

440

Operational Issues at the Environmental Restoration Disposal Facility at Hanford  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Operations Hanford Operations Evaluating Operational Issues at the Environmental Restoration Disposal Facility at Hanford By Craig H. Benson, PhD, PE; William H. Albright, PhD; and David P. Ray, PE Sponsored by: The Office of Engineering and Technology (EM-20) 17 June 2007 i TABLE OF CONTENTS EXECUTIVE SUMMARY ii ACKNOWLEDGEMENTS iv INTRODUCTION 1 BACKGROUND 1 Environmental Restoration Disposal Facility 1 Source of Concern 2 LINES OF INQUIRY 2 1. Validate Scope of Identified Problems 2 2. Assess Contractor Evaluation of the Elevated Leachate Level on the Landfill Liner 3 3. Evaluate Adequacy of Landfill Performance in View of the Discovered Falsified Compaction Data and Potential Leachate Level Problems 4

Note: This page contains sample records for the topic "disposal system header" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Delivers First Radioactive Waste Shipment to Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and

442

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis  

Science Conference Proceedings (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energyís mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-10-01T23:59:59.000Z

443

Drilling Waste Management Fact Sheet: Disposal in Salt Caverns  

NLE Websites -- All DOE Office Websites (Extended Search)

Salt Caverns Salt Caverns Fact Sheet - Disposal in Salt Caverns Introduction to Salt Caverns Underground salt deposits are found in the continental United States and worldwide. Salt domes are large, fingerlike projections of nearly pure salt that have risen to near the surface. Bedded salt formations typically contain multiple layers of salt separated by layers of other rocks. Salt beds occur at depths of 500 to more than 6,000 feet below the surface. Schematic Drawing click to view larger image Schematic Drawing of a Cavern in Domal Salt Schematic Drawing click to view larger image Schematic Drawing of a Cavern in Bedded Salt Salt caverns used for oil field waste disposal are created by a process called solution mining. Well drilling equipment is used to drill a hole

444

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Portsmouth Site Delivers First Radioactive Waste Shipment to Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the

445

Anaerobic digestion as a waste disposal option for American Samoa  

DOE Green Energy (OSTI)

Tuna sludge and municipal solid waste (MSW) generated on Tutuila Island, American Samoa, represent an ongoing disposal problem as well as an emerging opportunity for use in renewable fuel production. This research project focuses on the biological conversion of the organic fraction of these wastes to useful products including methane and fertilizer-grade residue through anaerobic high solids digestion. In this preliminary study, the anaerobic bioconversion of tuna sludge with MSW appears promising.

Rivard, C

1993-01-01T23:59:59.000Z

446

Subseabed Disposal Program. Annual report, January-December 1978  

Science Conference Proceedings (OSTI)

This is the fifth annual report describing the progress and evaluating the status of the Subseabed Disposal Program (SDP), which was begun in June 1973. The program was initiated by Sandia Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans.

Talbert, D.M. (ed.)

1980-02-01T23:59:59.000Z

447

Mixed waste characterization, treatment, and disposal focus area. Technology summary  

Science Conference Proceedings (OSTI)

This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

NONE

1995-06-01T23:59:59.000Z

448

Disposable Absorbent Material for the Removal of Arsenic from Water  

Science Conference Proceedings (OSTI)

Soils and groundwater at many substation sites are contaminated with arsenic-containing compounds. Cost effective water treatment technologies are needed to remove arsenic and other trace metals from underlying aquifers, especially now that drinking water standard for arsenic has been lowered to 10 g/L from the previous value of 50 g/L. The current project tested a disposable ferric oxide adsorbent material, Bayoxide E33, which has been reported to have a high capacity for arsenic removal.

2008-09-10T23:59:59.000Z

449

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers  

Science Conference Proceedings (OSTI)

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of high-level radioactive-waste disposal containers. The waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The copper-based alloy materials are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The austenitic materials are Types 304L and 316L stainless steels and Alloy 825. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr, and they must be retrievable from the disposal site during the first 50 yr after emplacement. The containers will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This volume surveys the available data on the phase stability of both groups of candidate alloys. The austenitic alloys are reviewed in terms of the physical metallurgy of the iron-chromium-nickel system, martensite transformations, carbide formation, and intermetallic-phase precipitation. The copper-based alloys are reviewed in terms of their phase equilibria and the possibility of precipitation of the minor alloying constituents. For the austenitic materials, the ranking based on phase stability is: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is: CDA 102 (oxygen-free copper) (best), and then both CDA 715 and CDA 613. 75 refs., 24 figs., 6 tabs.

Bullen, D.B.; Gdowski, G.E. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01T23:59:59.000Z

450

Disposal of EOR and waste fluids. Final report  

SciTech Connect

When enhanced oil recovery (EOR) chemicals and/or waste fluids are injected into deep wells for recovery of oil or for disposal, they may pose environmental problems. This report, based only on a study of the literature, discusses injection waters, water compatibilities, and formation rocks with emphasis on clay minerals, corrosion, bacterial problems, EOR operations, waste fluid injection operations, injection well design, radioactive wastes, transport and fate processes, and mathematical models. Environmental problems can result from petroleum production operations such as: (1) primary recovery, (2) secondary recovery, (3) tertiary and/or EOR, and (4) waste disposal. Present environmental laws and probable future amendments are such that the petroleum production industry and government should implement research in specific areas. For example, characterization of a waste disposal site with respect to a contaminant such as an EOR chemical involves not only characterization of the site (injection well and reservoir), but also the contaminant (the EOR chemical). The major environmental impacts associated with EOR are: (1) possible contamination of surface and ground water, (2) possible contamination of agricultural land, (3) use of potable water in EOR operations, and (4) possible contamination of air quality (primarily related to steamflooding). This report addresses items 1 and 2 above. 12 refs., 1 fig.

Collins, A.G.; Madden, M.P.

1986-06-01T23:59:59.000Z

451

Hanford land disposal restrictions plan for mixed wastes  

Science Conference Proceedings (OSTI)

Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs.

Not Available

1990-10-01T23:59:59.000Z

452

Iraq nuclear facility dismantlement and disposal project (NDs Project).  

SciTech Connect

The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

Cochran, John Russell

2010-06-01T23:59:59.000Z

453

Disposal criticality analysis methodology for fissile waste forms  

SciTech Connect

A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository.

Davis, J.W. [Framatome Cogema Fuels, Las Vegas, NV (United States); Gottlieb, P. [TRW Environmental Safety Systems, Las Vegas, NV (United States)

1998-03-01T23:59:59.000Z

454

Integrated Disposal Facility FY2010 Glass Testing Summary Report  

SciTech Connect

Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 ◊ 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 ◊ 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 ◊ 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

2010-09-30T23:59:59.000Z

455

Infectious waste feed system  

DOE Patents (OSTI)

An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

456

Disposal of Greater-than-Class C Low-Level Radioactive Waste  

NLE Websites -- All DOE Office Websites (Extended Search)

Disposal of Low-Level Radioactive Waste Disposal of Low-Level Radioactive Waste EVS prepared a draft environmental impact statement (EIS) for disposal of greater-than-Class C low-level radioactive waste (GTCC LLRW). The EVS Division prepared a draft environmental impact statement (EIS) for disposal of greater-than-Class C low-level radioactive waste (GTCC LLRW) for the DOE Office of Environmental Management. DOE is now finalizing this EIS and is including a preferred alternative. DOE intends that the final EIS will provide information to support the selection of disposal method(s) and site(s) for GTCC LLRW and GTCC-like waste. In general, GTCC LLRW is not acceptable for near-surface disposal. Typically, the waste form and disposal methods must be different from and more stringent than those specified for Class C LLRW. For GTCC LLRW, the

457

Standard-B hydrogen monitoring system acceptance test report  

DOE Green Energy (OSTI)

Test Engineering was supported by Tank Waste Remediation System Safety Programs Engineering Support in the performance of an Acceptance Test Procedure (ATP) to qualify the Standard Hydrogen Monitoring System (SHMS) cabinet installed on waste tank 241-SY-103. The June 7, 1994 ATP performance was controlled by West Waste Tank Farms work package 2W-94-322. The ATP was conducted following the final installation of a second Whittaker electro-chemical hydrogen monitoring cell. The cabinet had been sited on the waste tank two years earlier, but never connected to the exhaust vent header to monitor Tank 241-SY-103 vent header exhaust gases. The cabinet was then modified, to remove two undesirable solid state hydrogen monitors and install a second Whittaker electro-chemical hydrogen monitoring sensor and signal conditioning. The ATP was used to assure that the cabinet wiring and components were properly installed and labeled and that the two years without operation had not seriously damaged the installed equipment. Electrical and pneumatic tests were performed to assure system integrity.

Tran, T.T.

1994-09-08T23:59:59.000Z

458

The implications of UIC and NPDES regulations on selection of disposal options for spent geothermal brine  

Science Conference Proceedings (OSTI)

This document reviews and evaluates the various options for the disposal of geothermal wastewater with respect to the promulgated regulations for the protection of surface and groundwaters. The Clean Water Act of 1977 and the Safe Drinking Water Act Amendments are especially important when designing disposal systems for geothermal fluids. The former promulgates regulations concerning the discharge of wastewater into surface waters, while the latter is concerned with the protection of ground water aquifers through the establishment of underground injection control (UIC) programs. There is a specific category for geothermal fluid discharge if injection is to be used as a method of disposal. Prior to February 1982, the UIC regulations required geothermal power plant to use Class III wells and direct use plants to use Class V wells. More stringent regulatory requirements, including construction specification and monitoring, are imposed on the Class III wells. On February 3, 1982, the classification of geothermal injection wells was changed from a Class III to Class V on the basis that geothermal wells do not inject for the extraction of minerals or energy, but rather they are used to inject brines, from which heat has been extracted, into formations from which they were originally taken. This reclassification implies that a substantial cost reduction will be realized for geothermal fluid injection primarily because well monitoring is no longer mandatory. The Clean Water Act of 1977 provides the legal basis for regulating the discharge of liquid effluent into the nation's surface waters, through a permitting system called the National Pollution Discharge Elimination System (NPDES) Discharge quantities, rates, concentrations and temperatures are regulated by the NPDES permits. These permits systems are based upon effluent guidelines developed by EPA on an industry by industry basis. For geothermal energy industry, effluent guidelines have not been formulated and are not currently scheduled. There, are however, water quality standards that control the quantity and quality of wastewaters discharged into surface waters. These standards are established by the states in concert with EPA, and frequently result in NPDES conditions more restrictive than those based on effluent guidelines.

None

1982-07-01T23:59:59.000Z

459

Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal  

SciTech Connect

This Toxic Substances Control Act Risk-Based Polychlorinated Biphenyl Disposal plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex, Idaho National Laboratory Site, to address painted surfaces in the empty canal under 40 CFR 761.62(c) for paint, and under 40 CFR 761.61(c) for PCBs that may have penetrated into the concrete. The canal walls and floor will be painted with two coats of contrasting non-PCB paint and labeled as PCB. The canal is covered with open decking; the access grate is locked shut and signed to indicate PCB contamination in the canal. Access to the canal will require facility manager permission. Protective equipment for personnel and equipment entering the canal will be required. Waste from the canal, generated during ultimate Decontamination and Decommissioning, shall be managed and disposed as PCB Bulk Product Waste.

R. A. Montgomery

2008-05-01T23:59:59.000Z

460

Grout disposal facility vault exhauster: Technical background document on demonstration of best available control technology for toxics  

SciTech Connect

The Grout Disposal Facility (GDF) is currently operated on the US Department of Energy`s Hanford Site. The GDF is located near the east end of the Hanford Site`s 200 East operations area, and is used for the treatment and disposal of low-level radioactive liquid wastes. In the grout treatment process, selected radioactive wastes from double-shell tanks are mixed with grout-forming solids; the resulting grout slurry is pumped to near-surface concrete vaults for solidification and permanent disposal. As part of this treatment process, small amounts of toxic particles and volatile organic compounds (VOCs) may be released to the atmosphere through the GDF`s exhaust system. This analysis constitutes a Best Available Control Technology for Toxics (T-BACT) study, as required in the Washington Administrative Code (WAC 173-460) to support a Notice of Construction for the operation of the GDF exhaust system at a modified flow rate that exceeds the previously permitted value. This report accomplishes the following: assesses the potential emissions from the GDF; estimates air quality impacts to the public from toxic air pollutants; identifies control technologies that could reduce GDF emissions; evaluates impacts of the control technologies; and recommends appropriate emissions controls.

Glissmeyer, J.A.; Glantz, C.S. [Pacific Northwest Lab., Richland, WA (United States); Rittman, P.D. [Westinghouse Hanford Co., Richland, WA (United States)

1994-09-01T23:59:59.000Z

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