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Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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.


1

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A  

SciTech Connect (OSTI)

This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification.

Bowman, R.C.

1994-04-01T23:59:59.000Z

2

EA-1707: Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste  

Broader source: Energy.gov (indexed) [DOE]

07: Closure of Nonradioactive Dangerous Waste Landfill and 07: Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill, Hanford Site, Richland, Washington EA-1707: Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill, Hanford Site, Richland, Washington Summary This EA evaluates the potential environmental impacts of closing the Nonradioactive Dangerous Waste Landfill and the Solid Waste Landfill. The Washington State Department of Ecology is a cooperating agency in preparing this EA. Public Comment Opportunities None available at this time. Documents Available for Download August 26, 2011 EA-1707: Revised Draft Environmental Assessment Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill, Hanford Site, Richland, Washington May 13, 2010 EA-1707: Draft Environmental Assessment

3

EA-1707: Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the potential environmental impacts of closing the Nonradioactive Dangerous Waste Landfill and the Solid Waste Landfill. The Washington State Department of Ecology is a cooperating agency in preparing this EA.

4

2727-S Nonradioactive Dangerous Waste Storage Facility Closure Plan. Revision 3A  

SciTech Connect (OSTI)

This report contains Sections 4 and 5 of the Nonradioactive Dangerous Waste Storage Facility Closure Plan, which summarizes closure activities for the site. Sampling procedures for the building, concrete and soils are given. Plans for building disposal, equipment decontamination, site restoration, and providing cost estimates are outlined. Section 5 discusses plans to develop a health and safety contingency plan before initiation of sampling activities.

Not Available

1992-10-01T23:59:59.000Z

5

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

from tank waste. * Decreases the volume of water to create room in double-shell tanks, allowing them to accept waste from noncompliant single- shell tanks. * Treats up to 1...

6

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

trucks for scale. The DSTs have limited capacity and are aging. Maintaining these tanks is important to ensure that waste is ready to supply the Waste Treatment Plant. The...

7

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

training, security) * Closure plan Tank-Related Permit Units New * 149 single-shell tanks (SSTs) * 28 double-shell tanks (DSTs) Existing * 242-A Evaporator * Waste Treatment...

8

Hanford facility dangerous waste permit application  

SciTech Connect (OSTI)

This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit.

none,

1991-09-18T23:59:59.000Z

9

Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes  

SciTech Connect (OSTI)

This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

Dominick, J

2008-12-18T23:59:59.000Z

10

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

11

Status of the WAND (Waste Assay for Nonradioactive Disposal) project as of July 1997  

SciTech Connect (OSTI)

The WAND (Waste Assay for Nonradioactive Disposal) system can scan thought-to-be-clean, low-density waste (mostly paper and plastics) to determine whether the levels of any contaminant radioactivity are low enough to justify their disposal in normal public landfills or similar facilities. Such a screening would allow probably at least half of the large volume of low-density waste now buried at high cost in LANL`s Rad Waste Landfill (Area G at Technical Area 54) to be disposed of elsewhere at a much lower cost. The WAND System consists of a well-shielded bank of six 5-in.-diam. phoswich scintillation detectors; a mechanical conveyor system that carries a 12-in.-wide layer of either shredded material or packets of paper sheets beneath the bank of detectors; the electronics needed to process the outputs of the detectors; and a small computer to control the whole system and to perform the data analysis. WAND system minimum detectable activities (MDAs) for point sources range from {approximately}20 dps for {sup 241}Am to approximately 10 times that value for {sup 239}Pu, with most other nuclides of interest being between those values, depending upon the emission probabilities of the radiations emitted (usually gamma rays and/or x-rays). The system can also detect beta particles that have energies {ge}100 keV, but it is not easy to define an MDA based on beta radiation detection because of the greater absorption of beta particles relative to photons in low Z-materials. The only radioactive nuclides not detectable by the WAND system are pure alpha emitters and very-low-energy beta emitters. At this time, operating procedures and quality assurance procedures are in place and training materials are available to operators. The system is ready to perform useful work; however, it would be both possible and desirable to upgrade the electronic components and the analysis algorithms.

Arnone, G.J.; Foster, L.A.; Foxx, C.L.; Hagan, R.C.; Martin, E.R.; Myers, S.C.; Parker, J.L.

1998-03-01T23:59:59.000Z

12

Data quality objective for regulatory requirements for dangerous waste sampling and analysis  

SciTech Connect (OSTI)

Contains requirements for sampling and analysis to meet the dangerous (hazardous) waste regulations.

Mulkey, C.H., Westinghouse Hanford

1996-07-02T23:59:59.000Z

13

Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

Transuranic (TRU) waste generated by the handling of plutonium in research on or production of US nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m{sup 3} of TRU waste, corresponding to 168,485 m{sup 3} of contact-handled (CH-) TRU waste and 7,079 m{sup 3} of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 US Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM).

SANCHEZ,LAWRENCE C.; DREZ,P.E.; RATH,JONATHAN S.; TRELLUE,H.R.

2000-05-19T23:59:59.000Z

14

Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)  

SciTech Connect (OSTI)

This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas.

SIMMONS, F.M.

2000-03-29T23:59:59.000Z

15

2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report  

SciTech Connect (OSTI)

This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation.

Luke, S.N.

1994-07-14T23:59:59.000Z

16

Plutonium finishing plant dangerous waste training plan  

SciTech Connect (OSTI)

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas.

ENTROP, G.E.

1999-05-24T23:59:59.000Z

17

Hanford facility dangerous waste permit application, general information portion  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report).

Hays, C.B.

1998-05-19T23:59:59.000Z

18

Full-scale tests of sulfur polymer cement and non-radioactive waste in heated and unheated prototypical containers  

SciTech Connect (OSTI)

Sulfur polymer cement has been demonstrated to be superior to portland cement in the stabilization of numerous troublesome low- level radioactive wastes, notably mixed waste fly ash, which contains heavy metals. EG G Idaho, Inc. conducted full-scale, waste-stabilization tests with a mixture of sulfur polymer cement and nonradioactive incinerator ash poured over simulated steel and ash wastes. The container used to contain the simulated waste for the pour was a thin-walled, rectangular, steel container with no appendages. The variable in the tests was that one container and its contents were at 65{degree}F (18{degree}C) at the beginning of the pour, while the other was preheated to 275{degree}F (135{degree}C) and was insulated before the pour. The primary goal was to determine the procedures and equipment deemed operationally acceptable and capable of providing the best probability of passing the only remaining governmental test for sulfur polymer cement, the Nuclear Regulatory Commission's full-scale test. The secondary goal was to analyze the ability of the molten cement and ash mixture to fill different size pipes and thus eliminate voids in the resultant 24 ft{sup 3} monolith.

Darnell, G.R.; Aldrich, W.C.; Logan, J.A.

1992-02-01T23:59:59.000Z

19

Full-scale tests of sulfur polymer cement and non-radioactive waste in heated and unheated prototypical containers  

SciTech Connect (OSTI)

Sulfur polymer cement has been demonstrated to be superior to portland cement in the stabilization of numerous troublesome low- level radioactive wastes, notably mixed waste fly ash, which contains heavy metals. EG&G Idaho, Inc. conducted full-scale, waste-stabilization tests with a mixture of sulfur polymer cement and nonradioactive incinerator ash poured over simulated steel and ash wastes. The container used to contain the simulated waste for the pour was a thin-walled, rectangular, steel container with no appendages. The variable in the tests was that one container and its contents were at 65{degree}F (18{degree}C) at the beginning of the pour, while the other was preheated to 275{degree}F (135{degree}C) and was insulated before the pour. The primary goal was to determine the procedures and equipment deemed operationally acceptable and capable of providing the best probability of passing the only remaining governmental test for sulfur polymer cement, the Nuclear Regulatory Commission`s full-scale test. The secondary goal was to analyze the ability of the molten cement and ash mixture to fill different size pipes and thus eliminate voids in the resultant 24 ft{sup 3} monolith.

Darnell, G.R.; Aldrich, W.C.; Logan, J.A.

1992-02-01T23:59:59.000Z

20

Hanford Facility dangerous waste permit application, general information. Revision 1  

SciTech Connect (OSTI)

The current Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, number DOE/RL-91-28) and a treatment, storage, and/or disposal Unit-Specific Portion, which includes documentation for individual TSD units (e.g., document numbers DOE/RL-89-03 and DOE/RL-90-01). Both portions consist of a Part A division and a Part B division. The Part B division consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. Documentation contained in the General Information Portion (i.e., this document, number DOE/RL-91-28) is broader in nature and applies to all treatment, storage, and/or disposal units for which final status is sought. Because of its broad nature, the Part A division of the General Information Portion references the Hanford Facility Dangerous Waste Part A Permit Application (document number DOE/RL-88-21), a compilation of all Part A documentation for the Hanford Facility.

Not Available

1993-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Hanford facility dangerous waste permit application, general information portion  

SciTech Connect (OSTI)

The `Hanford Facility Dangerous Waste Permit Application` is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit- Specific Portion. The scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, and/or disposal unit-specific Part B permit application, preclosure work plan, closure work plan, closure plan, closure/postclosure plan, or postclosure permit application documentation development, and the `Hanford Facility Resource Conservation and Recovery Act Permit` modification process. Revision 2 of the General Information Portion of the `Hanford Facility Dangerous Waste Permit Application` contains information current as of May 1, 1996. This document is a complete submittal and supersedes Revision 1.

Price, S.M., Westinghouse Hanford

1996-07-29T23:59:59.000Z

22

Hanford facility dangerous waste permit application, PUREX storage tunnels  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997.

Price, S.M.

1997-09-08T23:59:59.000Z

23

GRR/Section 18-WA-b - Dangerous Waste Permit | Open Energy Information  

Open Energy Info (EERE)

GRR/Section 18-WA-b - Dangerous Waste Permit GRR/Section 18-WA-b - Dangerous Waste Permit < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-WA-b - Dangerous Waste Permit 18-WA-b - Dangerous Waste Permit.pdf Click to View Fullscreen Contact Agencies Washington State Department of Ecology Regulations & Policies WAC 173-303-020 WAC 173-303-060 WAC 173-303-070 WAC 173-303-071 WAC 173-303-072 WAC 173-303-081 WAC 173-303-082 WAC 173-303-090 WAC 173-303-100 WAC 173-303-110 WAC 173-303-140 WAC 173-303-220 WAC 173-303-281 WAC 173-303-282 WAC 173-303-803 WAC 173-303-845 Triggers None specified The Washington State Department of Ecology (WSDE) oversees the permitting process for dangerous and solid waste. In Washington, a developer must obtain a permit if they handle dangerous waste and solid waste and are

24

Letter report: Pre-conceptual design study for a pilot-scale Non-Radioactive Low-Level Waste Vitrification Facility  

SciTech Connect (OSTI)

This report presents a pre-conceptual design study for a Non-Radioactive Low-Level Waste, Pilot-Scale Vitrification System. This pilot plant would support the development of a full-scale LLW Vitrification Facility and would ensure that the full-scale facility can meet its programmatic objectives. Use of the pilot facility will allow verification of process flowsheets, provide data for ensuring product quality, assist in scaling to full scale, and support full-scale start-up. The facility will vitrify simulated non-radioactive LLW in a manner functionally prototypic to the full-scale facility. This pre-conceptual design study does not fully define the LLW Pilot-Scale Vitrification System; rather, it estimates the funding required to build such a facility. This study includes identifying all equipment necessary. to prepare feed, deliver it into the melter, convert the feed to glass, prepare emissions for atmospheric release, and discharge and handle the glass. The conceived pilot facility includes support services and a structure to contain process equipment.

Thompson, R.A.; Morrissey, M.F.

1996-03-01T23:59:59.000Z

25

Hanford facility dangerous waste permit application, general information portion. Revision 3  

SciTech Connect (OSTI)

For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy`s contractors are identified as ``co-operators`` and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ``operator`` elsewhere in the application is not meant to conflict with the contractors` designation as co-operators but rather is based on the contractors` contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which Part B permit application documentation has been, or is anticipated to be, submitted. Documentation for treatment, storage, and/or disposal units undergoing closure, or for units that are, or are anticipated to be, dispositioned through other options, will continue to be submitted by the Permittees in accordance with the provisions of the Hanford Federal Facility Agreement and Consent Order. However, the scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the contents of the Part B permit application guidance documentation prepared by the Washington State Department of Ecology and the U.S. Environmental Protection Agency, with additional information needs defined by revisions of Washington Administrative Code 173-303 and by the Hazardous and Solid Waste Amendments. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (i.e., either operating units, units undergoing closure, or units being dispositioned through other options).

Sonnichsen, J.C.

1997-08-21T23:59:59.000Z

26

Data Quality Objectives for Regulatory Requirements for Dangerous Waste Sampling and Analysis  

SciTech Connect (OSTI)

This document describes sampling and analytical requirements needed to meet state and federal regulations for dangerous waste (DW). The River Protection Project (RPP) is assigned to the task of storage and interim treatment of hazardous waste. Any final treatment or disposal operations, as well as requirements under the land disposal restrictions (LDRs), fall in the jurisdiction of another Hanford organization and are not part of this scope. The requirements for this Data Quality Objective (DQO) Process were developed using the RPP Data Quality Objective Procedure (Banning 1996), which is based on the U.S. Environmental Protection Agency's (EPA) Guidance for the Data Quality Objectives Process (EPA 1994). Hereafter, this document is referred to as the DW DQO. Federal and state laws and regulations pertaining to waste contain requirements that are dependent upon the composition of the waste stream. These regulatory drivers require that pertinent information be obtained. For many requirements, documented process knowledge of a waste composition can be used instead of analytical data to characterize or designate a waste. When process knowledge alone is used to characterize a waste, it is a best management practice to validate the information with analytical measurements.

MULKEY, C.H.

1999-07-02T23:59:59.000Z

27

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating text. 38 39 Information provided in this Liquid Effluent Retention Facility and 40 200 Area Effluent Treatment Facility permit application documentation is 41 current as of June 1, 1997.

Coenenberg, J.G.

1997-08-15T23:59:59.000Z

28

E-Print Network 3.0 - annual dangerous waste Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

wastes in the form of gases and ash, often creating entirely new hazards, like dioxins and furans... Zero Waste, Renewable Energy & Environmental Stewardship - Connecting...

29

Hanford facility dangerous waste permit application, low-level burial grounds  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Plaste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, `operating` treatment, storage, and/or disposal units, such as the Low-Level Burial Grounds (this document, DOE/RL-88-20).

Engelmann, R.H.

1997-08-12T23:59:59.000Z

30

Nonradioactive demonstration of the Alpha D and D Pilot Facility  

SciTech Connect (OSTI)

The Alpha-Contained Decontamination and Disassembly (AD and D) pilot facility was designed to demonstrate the process flowsheet under conditions typical to those expected in a production facility. To achieve this, nonradioactive waste items similar to those in retrievable storage at the Savannah River Plant burial ground (e.g. gloveboxes), were chemically sprayed and size reduced. During process runs, parameters such as feed rate, oxide removal, etching rate, and secondary waste generation were determined. The exhaust system was monitored during operation to ensure that exhaust from the facility was sufficiently filtered before release to the atmosphere. The strategy for decontamination techniques required development during the nonradioactive testing period. Under investigation during process runs were both once-through and recirculating washes, and their correlation to oxide removal and etching rates on the stainless steel feed items. Wash products of the decontamination process were analyzed for concentration of Ni, Cr, Fe, Mn, and Si, major components of stainless steel. Size reduction techniques were also developed during the nonradioactive testing period. An array of conventional power and pneumatic tools were tested and evaluated. Plasma arc torch operating parameters; standoff distance, ampere setting, and cutting angle were determined.

Wobser, J.K.

1983-01-01T23:59:59.000Z

31

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Single-Shell Tank System Closing Unit 4 The tanks and surrounding contaminated soil are one of Hanford's greatest challenges. We don't really know the full extent of the risks...

32

Danger radiations  

ScienceCinema (OSTI)

Le conférencier Mons.Hofert parle des dangers et risques des radiations, le contrôle des zones et les précautions à prendre ( p.ex. film badge), comment mesurer les radiations etc.

None

2011-04-25T23:59:59.000Z

33

Recycling of sodium waste  

Science Journals Connector (OSTI)

Recycling of sodium waste ... Methods for handling and recycling a dangerous and costly chemical. ...

Bettina Hubler-Blank; Michael Witt; Herbert W. Roesky

1993-01-01T23:59:59.000Z

34

Georgia Tech Dangerous Gas  

E-Print Network [OSTI]

1 Georgia Tech Dangerous Gas Safety Program March 2011 #12;Georgia Tech Dangerous Gas Safety.......................................................................................................... 5 6. DANGEROUS GAS USAGE REQUIREMENTS................................................. 7 6.1. RESTRICTED PURCHASE/ACQUISITION RULES: ................................................ 7 7. FLAMMABLE GAS

Sherrill, David

35

The dangers of extremes  

E-Print Network [OSTI]

of quantum corrections to extreme black holes indicate noeffects [10]. The dangers of extremes 8. Ori, A. : StructureFOUNDATION The dangers of extremes Donald Marolf Published

Marolf, Donald

2010-01-01T23:59:59.000Z

36

Rev August 2006 Radiation Safety Manual Section 14 Radioactive Waste  

E-Print Network [OSTI]

Rev August 2006 Radiation Safety Manual Section 14 ­ Radioactive Waste Page 14-1 Section 14 Radioactive Waste Contents A. Proper Collection, Disposal, and Packaging and Putrescible Animal Waste.........................14-8 a. Non-Radioactive Animal Waste

Wilcock, William

37

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect (OSTI)

This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

VOLKMAN, D.D.

1999-10-27T23:59:59.000Z

38

How dangerous is chemistry?  

Science Journals Connector (OSTI)

... Is chemistry really so dangerous? Those responsible for the safety of research labs say such stories may perpetuate out- ... says Alan Kendall, safety officer at the University of Oxford, UK. Swathes of occupational-health legislation in the 1970s, which established, for example, the US government's Occupational ...

2006-05-31T23:59:59.000Z

39

More dangerous smallpox labs?  

Science Journals Connector (OSTI)

... As FAR as the World Health Organisa-tion (WHO) is aware there are now nine laboratories in the world holding ... the prevention of infection in clinical laboratories, not the Godber report on the handling of dangerous pathogens, as indicated in last week's leader. ...

1979-01-18T23:59:59.000Z

40

1DANGEROUS CLIMATE CHANGE IN BRAZIL Dangerous Climate  

E-Print Network [OSTI]

1DANGEROUS CLIMATE CHANGE IN BRAZIL Dangerous Climate A BrAzil-UK AnAlysis of ClimAte ChAnge And deforestAtion impACts in the AmAzon Change in Brazil #12;3DANGEROUS CLIMATE CHANGE IN BRAZIL April 2011Alysis of ClimAte ChAnge And deforestAtion impACts in the AmAzon Change in Brazil #12;4 DANGEROUS CLIMATE CHANGE

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Dangerous electromagnetic fields?  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Dangerous electromagnetic fields? Dangerous electromagnetic fields? Name: Tommy T Joseph Location: N/A Country: N/A Date: N/A Question: Why are electromagnetic fields supposedly dangerous? Replies: I assume you are asking about power line frequency (60 Hz) fields, since they have been in the news lately. No one knows for sure that they are dangerous. There have been a few studies which seem to show an association between how close homes are to power lines, and the incidence of childhood cancer (mostly leukemia) in children living (or who have lived) in those homes. Other similar studies have not found such an association. In all the studies which have found an association, none has actually measured the fields. Studies which actually have measured the fields find no association. There is no known mechanism for 60 Hz fields to cause cancer. Furthermore, the classic "dose-response relationship," that is, the greater the dose, the greater the response, does not seem to work here. Many laboratory studies have found that 60 Hz fields have an effect on organisms under certain conditions, but none of the observed effects can be convincingly related to a hazard. The bottom line is, no one knows for sure. It is important to realize that it is impossible to prove that anything is completely safe. My personal opinion is that, if there is a risk, it must be very small, or it wouldn't be so hard to prove. I can supply some good unbiased references if you are interested.

42

Fact Sheet  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

impacts of proposed closure activities for the Nonradioactive Dangerous Waste Landfill (NRDWL) and the Solid Waste Landfill (SWL). We want your input What is the...

43

Slide 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Environmental Assessment for Closing Hanford's Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill The U.S. Department of Energy (DOE) is issuing a National...

44

EA-1707: Draft Environmental Assessment | Department of Energy  

Office of Environmental Management (EM)

EA-1707: Draft Environmental Assessment Closure of Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill, Hanford Site, Richland, Washington This environmental...

45

Detection of rotavirus by hybridization with a nonradioactive synthetic DNA probe and comparison with commercial enzyme immunoassays and silver-stained polyacrylamide gels.  

Science Journals Connector (OSTI)

...hybridization with a nonradioactive synthetic DNA probe and comparison with commercial...hybridization with a nonradioactive synthetic DNA probe and comparison with commercial...Hybridization with a Nonradioactive Synthetic DNA Probe and Comparison with Commercial...

M Arens; E M Swierkosz

1989-06-01T23:59:59.000Z

46

HOW DANGEROUS IS INDOOR MOLD?  

Science Journals Connector (OSTI)

HOW DANGEROUS IS INDOOR MOLD? ... Media coverage, litigation, and health concerns relating to indoor mold have dramatically risen over the past decade. ...

LOUISA WRAY DALTON

2004-02-16T23:59:59.000Z

47

Hanford Site background: Part 1, Soil background for nonradioactive analytes. Revision 1, Volume 1  

SciTech Connect (OSTI)

The determination of soil background is one of the most important activities supporting environmental restoration and waste management on the Hanford Site. Background compositions serve as the basis for identifying soil contamination, and also as a baseline in risk assessment processes used to determine soil cleanup and treatment levels. These uses of soil background require an understanding of the extent to which analytes of concern occur naturally in the soils. This report documents the results of sampling and analysis activities designed to characterize the composition of soil background at the Hanford Site, and to evaluate the feasibility for use as Sitewide background. The compositions of naturally occurring soils in the vadose Zone have been-determined for-nonradioactive inorganic and organic analytes and related physical properties. These results confirm that a Sitewide approach to the characterization of soil background is technically sound and is a viable alternative to the determination and use of numerous local or area backgrounds that yield inconsistent definitions of contamination. Sitewide soil background consists of several types of data and is appropriate for use in identifying contamination in all soils in the vadose zone on the Hanford Site. The natural concentrations of nearly every inorganic analyte extend to levels that exceed calculated health-based cleanup limits. The levels of most inorganic analytes, however, are well below these health-based limits. The highest measured background concentrations occur in three volumetrically minor soil types, the most important of which are topsoils adjacent to the Columbia River that are rich in organic carbon. No organic analyte levels above detection were found in any of the soil samples.

Not Available

1993-04-01T23:59:59.000Z

48

Report on AOAC, Narcotic and Dangerous Drugs  

Science Journals Connector (OSTI)

......Report on AOAC, narcotic and dangerous drugs. | Journal Article...Report on AOAC, Narcotic and Dangerous Drugs by Anthony Romano...Bureau of Narcotics and Dangerous Drugs, Miami, Florida 33132...substances affect- ing public health." The AOAC itself maintains......

Anthony Romano; Jr.

1972-05-01T23:59:59.000Z

49

Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1  

SciTech Connect (OSTI)

This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond.

NONE

1995-09-01T23:59:59.000Z

50

Zero Waste, Renewable Energy & Environmental  

E-Print Network [OSTI]

· Dioxins & Furans · The `State of Waste' in the US · WTE Technologies · Thermal Recycling ­ Turnkey dangerous wastes in the form of gases and ash, often creating entirely new hazards, like dioxins and furans

Columbia University

51

1993 Solid Waste Reference Forecast Summary  

SciTech Connect (OSTI)

This report, which updates WHC-EP-0567, 1992 Solid Waste Reference Forecast Summary, (WHC 1992) forecasts the volumes of solid wastes to be generated or received at the US Department of Energy Hanford Site during the 30-year period from FY 1993 through FY 2022. The data used in this document were collected from Westinghouse Hanford Company forecasts as well as from surveys of waste generators at other US Department of Energy sites who are now shipping or plan to ship solid wastes to the Hanford Site for disposal. These wastes include low-level and low-level mixed waste, transuranic and transuranic mixed waste, and nonradioactive hazardous waste.

Valero, O.J.; Blackburn, C.L. [Westinghouse Hanford Co., Richland, WA (United States); Kaae, P.S.; Armacost, L.L.; Garrett, S.M.K. [Pacific Northwest Lab., Richland, WA (United States)

1993-08-01T23:59:59.000Z

52

Dangerous jellyfish blooms are predictable  

Science Journals Connector (OSTI)

...reserved. July 6, 2014 brief-report Reports 1004 27 69 Dangerous jellyfish blooms are predictable Lisa-ann Gershwin 1 Scott...Irukandji syndrome in northern Western Australia: an emerging health problem. Med. J. Aus. 181, 699-702. 7 Nickson, CP...

2014-01-01T23:59:59.000Z

53

Dangerous pathogens: New UK committee  

Science Journals Connector (OSTI)

... The long-awaited reorganization of the British mechanism for regulating research with dangerous pathogens is planned for early in 1981. Last week the Department of ... pathogens is planned for early in 1981. Last week the Department of Health and the ...

1980-10-30T23:59:59.000Z

54

Nevada National Security Site Waste Acceptance Criteria  

SciTech Connect (OSTI)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

NSTec Environmental Management

2012-02-28T23:59:59.000Z

55

Dangerous behavior and changes in treatment course  

Science Journals Connector (OSTI)

The association of dangerous behavior with the course of subsequent treatment was examined by comparing treatment courses of 45 severely mentally disabled patients identified as dangerous after an incident of ...

A. Michael Rossi Ph.D.; William A. Hargreaves Ph.D.…

1989-01-01T23:59:59.000Z

56

Application of a Nonradioactive Pulsed Electron Source for Ion Mobility Spectrometry  

Science Journals Connector (OSTI)

The concept of the new electron source used here is based on the early work (1894) of P. Lenard who showed that electrons, generated in an electrical discharge tube, could pass through a thin aluminum foil. ... In contrast to radioactive sources which constantly produce free electrons, this nonradioactive source allows for the introduction of delay times between the ion formation process and the ion extraction in which no free electrons are being produced. ...

Frank Gunzer; Stefan Zimmermann; Wolfgang Baether

2010-03-30T23:59:59.000Z

57

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

58

On Going TRU Waste Disposition  

SciTech Connect (OSTI)

The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

59

The presumption of dangerousness in sexually violent predator commitment proceedings  

Science Journals Connector (OSTI)

......presumption of not dangerous in civil proceedings...Department of Mental Health conducted an...department of mental health selects and refers relatively dangerous individuals...respondent is dangerous, the legal...Department of Health Services if......

Nicholas Scurich; Daniel A. Krauss

2014-03-01T23:59:59.000Z

60

EIS-0133: Decontamination and Waste Treatment Facility for the Lawrence Livermore National Laboratory Livermore, California  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy’s San Francisco Operations Office developed this statement to analyze the potential environmental and socioeconomic impacts of alternatives for constructing and operating a Decontamination and Waste Treatment Facility for nonradioactive (hazardous and nonhazardous) mixed and radioactive wastes at Lawrence Livermore National Laboratory.

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly.

ELLEFSON, M.D.

2000-01-06T23:59:59.000Z

62

Hanford Site solid waste acceptance criteria  

SciTech Connect (OSTI)

Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

Ellefson, M.D.

1998-07-01T23:59:59.000Z

63

Angry heart flutters prove most dangerous  

Science Journals Connector (OSTI)

... a study of people with cardiac troubles suggests that bursts of anger precede the most dangerous flutters of the heart. "We know that the emotional distress brought on by earthquakes ... attacks and even the loss of key football matches can trigger heart attacks," says health psychologist Doug Carroll of the University of Birmingham, UK. "It had been presumed ...

Roxanne Khamsi

2005-05-05T23:59:59.000Z

64

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2  

SciTech Connect (OSTI)

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

Jacobsen, P.H.

1997-09-23T23:59:59.000Z

65

E-Print Network 3.0 - american studies dangers Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

american studies dangers Page: << < 1 2 3 4 5 > >> 1 DEFINING AND EXPERIENCING DANGEROUS CLIMATE CHANGE An Editorial Essay Summary: and dangerous climate change include revealed...

66

E-Print Network 3.0 - assessing dangerous climate Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

dangerous climate Page: << < 1 2 3 4 5 > >> 1 DEFINING AND EXPERIENCING DANGEROUS CLIMATE CHANGE An Editorial Essay Summary: DEFINING AND EXPERIENCING DANGEROUS CLIMATE...

67

Categorical Exclusion for Emergency Danger Tree  

Broader source: Energy.gov (indexed) [DOE]

Danger Tree Danger Tree Removal along the Pinnacle Peak - Prescott 230-kV Transmission line between structures 216/4 & 216/5 & the adjacent Pinnacle Peak Substation, Maricopa County, Arizona. RECORD OF CATEGORICAL EXCLUSION DETERMINATION A. Proposed Action: Western proposes to cut down or trim vegetation that impacts worker safety and the reliable transmission of electricity on the existing Pinnacle Peak to Prescott 230-kV transmission line between Structures 216/4 and 216/5 in Maricopa County, Arizona. This emergency work must be completed before the line is energerized on March 21, 2010. Portions of several palo verde trees and one-to-three saguaros are less than 23 feet from the conductor, which is the minimum safe-distance for a 230-kV transmission

68

Dangerous Substances and Processes: Consideration of the Subject within the Educational Process  

Science Journals Connector (OSTI)

Abstract The education and training associated with Occupational Health and Safety (OHS) is a tool for the systematic forming and developing of science and professional knowledge and skills. The field of OHS aims at decreasing the accident and injury rate, making use of risk assessment and precautionary measures in terms of progressive arrangements from practice, education and the development of understanding. These factors lead to a complex improvement in welfare, an increase in the “culture of work” and school preparation. The evaluation of the dangers and risks associated with various types of chemical materials and chemical mixtures needs to be understood, together with the situations in which and why they are dangerous. The risks may exist when they are in the form of side products, such as in the form of waste materials within production technologies and processes. That is why it is essential to know the dangers involved and to keep the rules that ensure safe working with chemical materials and mixtures. The paper shows how important the discipline of “dangerous substances and processes” is in education and in the training process of future graduates in the Bachelor degree programme in Occupational Health and Safety in the Workplace.

Melánia Feszterová

2014-01-01T23:59:59.000Z

69

Synergistic Inhibitors for Dilute High-Level Radioactive Waste  

SciTech Connect (OSTI)

Cyclic potentiodynamic polarization scans were conducted to determine the effectiveness of various combinations of anodic inhibitors in the prevention of pitting in carbon steel exposed to dilute radioactive waste. Chromate, molybdate, and phosphate were investigated as replacements for nitrite, whose effective concentrations are incompatible with the waste vitrification process. The polarization scans were performed in non-radioactive waste simulants. Their results showed that acceptable combinations of phosphate with chromate and phosphate with molybdate effectively prevented pitting corrosion. Chromate with molybdate could not replace nitrite.

Wiersma, B.J.; Zapp, P.E.

1995-11-01T23:59:59.000Z

70

Questions and Answers - Is krypton dangerous?  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

does krypton look like? does krypton look like? Previous Question (What does krypton look like?) Questions and Answers Main Index Next Question (Why aren't Cl-35 and Cl-37 two different elements?) Why aren't Cl-35 and Cl-37two different elements? Is krypton dangerous? Krypton is a gas that is found in small amounts in the earth's atmosphere. Krypton's atomic structure is very stable. It has just enough electrons to fill its outer 'shell', so it doesn't tend to combine with other elements. Since it doesn't combine with other elements, it doesn't take part in chemical reactions, so it will not burn, cause corrosion, or do other chemical-like things. It is, however, possible for krypton to hurt you. If, for example, a room were to be filled with krypton, anyone entering the room would most likely

71

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

TRINER, G.C.

1999-11-01T23:59:59.000Z

72

PUREX Plant waste analysis plan. Revision 2  

SciTech Connect (OSTI)

A Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous wastes are managed properly. This document covers the activities at the PUREX Plant to characterize the designate waste that is generated within the plant, stored in Tanks F18, U3/U4, and managed through elementary neutralization in Tank 31.

Villalobos, C.N.

1995-04-10T23:59:59.000Z

73

Waste Treatment Plant Overview  

Broader source: Energy.gov (indexed) [DOE]

Hanford Site, located in southeastern Washington state, Hanford Site, located in southeastern Washington state, was the largest of three defense production sites in the U.S. Over the span of 40 years, it was used to produce 64 metric tons of plutonium, helping end World War II and playing a major role in military defense efforts during the Cold War. As a result, 56 million gallons of radioactive and chemical wastes are now stored in 177 underground tanks on the Hanford Site. To address this challenge, the U.S. Department of Energy contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the "Vit Plant," will use vitrification to immobilize most of Hanford's dangerous tank waste.

74

Review of CANDU NPP environmental releases and waste production: Current experience and future initiatives  

SciTech Connect (OSTI)

The characterization and sources of nuclear waste effluents arising from CANDU nuclear power plants will be reviewed. The design of the CANDU plant is based on the as low as reasonably achievable (ALARA) principle. Operation has shown that the CANDU plants easily meet regulatory limits and generally operate at the utility set target of one percent of this limit. There is increasing emphasis both within Canada and internationally to reduce environmental releases. Steps are being taken at operating CANDU plants and on future CANDU designs to achieve waste reduction or elimination, to introduce more effective waste handling methods and to improve treatment of radioactive and non-radioactive waste.

Barber, D.; Shalaby, B.A. [AECL CANDU, Mississauga, Ontario (Canada); Buckley, L.P. [AECL Research, Chalk River, Ontario (Canada)

1993-12-31T23:59:59.000Z

75

Waste management project fiscal year 1998 multi-year work plan WBS 1.2  

SciTech Connect (OSTI)

The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

Slaybaugh, R.R.

1997-08-29T23:59:59.000Z

76

SRNL CRP progress report [Development of Melt Processed Ceramics for Nuclear Waste Immobilization  

SciTech Connect (OSTI)

A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multiphase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing.

Amoroso, J.; Marra, J.

2014-10-02T23:59:59.000Z

77

Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992  

SciTech Connect (OSTI)

This report is DOE`s first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992.

Not Available

1994-02-01T23:59:59.000Z

78

RESORCINOL-FORMALDEHYDE ADSORPTION OF CESIUM (Cs+) FROM HANFORD WASTE SOLUTIONS-PART I: BATCH EQUILIBRIUM STUDY  

SciTech Connect (OSTI)

Batch equilibrium measurements were conducted with a granular Resorcinol-Formaldehyde (RF) resin to determine the distribution coefficients (Kds) for cesium. In the tests, Hanford Site actual waste sample containing radioactive cesium and a pretreated waste sample that was spiked with non-radioactive cesium were used. Initial concentrations of non-radioactive cesium in the waste sample were varied to generate an equilibrium isotherm for cesium. Two additional tests were conducted using a liquid to solid phase ratio of 10 and a contact time of 120 hours. The measured distribution coefficient (Kd) for radioactive cesium (137Cs) was 948 mL/g; the Kd for non-radioactive cesium (133Cs) was 1039 mL/g. The Kd for non-radioactive cesium decreased from 1039 to 691 mL/g as the initial cesium concentration increased. Very little change of the Kd was observed at initial cesium concentrations above 64 mg/mL. The maximum sorption capacity for cesium on granular RF resin was 1.17 mmole/g dry resin. T his value was calculated from the fit of the equilibrium isotherm data to the Dubinin-Radushkevich equation. Previously, a total capacity of 2.84 mmole/g was calculated by Bibler and Wallace for air-dried RF resin.

HASSAN, NEGUIBM

2004-03-30T23:59:59.000Z

79

E-Print Network 3.0 - avoiding dangerous climate Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

dangerous climate Page: << < 1 2 3 4 5 > >> 1 DEFINING AND EXPERIENCING DANGEROUS CLIMATE CHANGE An Editorial Essay Summary: Nations Framework Convention on Climate Change...

80

E-Print Network 3.0 - avoid dangerous climate Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

avoid dangerous climate Page: << < 1 2 3 4 5 > >> 1 DEFINING AND EXPERIENCING DANGEROUS CLIMATE CHANGE An Editorial Essay Summary: Nations Framework Convention on Climate Change...

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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.


81

Doing the Difficult and Dangerous: The Community Program Practice Scale  

Science Journals Connector (OSTI)

In an editorial about measuring fidelity to program models, Bickman (2000...) warned that describing services is our most difficult and dangerous task as mental health services researchers. It is difficult, Bickm...

William A. Hargreaves; Jeanette M. Jerrell…

2007-03-01T23:59:59.000Z

82

Giant Hogweed An attractive but dangerous federal noxious weed.  

E-Print Network [OSTI]

(1) Giant Hogweed An attractive but dangerous federal noxious weed. Have you seen this plant attractive, giant hogweed is a public health hazard because it can cause se- vere skin irritation

83

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM  

SciTech Connect (OSTI)

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02T23:59:59.000Z

84

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

85

Hanford Tank Waste Residuals  

Broader source: Energy.gov (indexed) [DOE]

Hanford Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - ~27 million gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

86

Naturally Dangerous: Surprising Facts about Food, Health, and the Environment (Collman, James P.)  

Science Journals Connector (OSTI)

Naturally Dangerous: Surprising Facts about Food, Health, and the Environment (Collman, James P.) ...

Harold H. Harris

2002-01-01T23:59:59.000Z

87

Comparative Health Risks of Domestic Waste Combustion in Urban and Rural Slovakia  

Science Journals Connector (OSTI)

Comparative Health Risks of Domestic Waste Combustion in Urban and Rural Slovakia ... Another dangerous impact of open burning is supported by the premature mortality increases which are attributable to exposures to PM2.5. ...

Jana Kraj?ovi?ová; Alan Q. Eschenroeder

2007-08-28T23:59:59.000Z

88

Keeping Tabs on the World's Dangerous Chemicals | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Keeping Tabs on the World's Dangerous Chemicals Keeping Tabs on the World's Dangerous Chemicals Keeping Tabs on the World's Dangerous Chemicals March 20, 2013 - 5:07pm Addthis Sandia chemical engineer Nancy Jackson has worked in laboratories around the world to help ensure that chemicals are used safely and kept secure. The American Association for the Advancement of Science honored her with the 2013 Science Diplomacy Award. | Photo by Randy Montoya, Sandia National Lab. Sandia chemical engineer Nancy Jackson has worked in laboratories around the world to help ensure that chemicals are used safely and kept secure. The American Association for the Advancement of Science honored her with the 2013 Science Diplomacy Award. | Photo by Randy Montoya, Sandia National Lab. Stephanie Hobby Media Relations, Sandia National Lab

89

Keeping Tabs on the World's Dangerous Chemicals | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Keeping Tabs on the World's Dangerous Chemicals Keeping Tabs on the World's Dangerous Chemicals Keeping Tabs on the World's Dangerous Chemicals March 20, 2013 - 5:07pm Addthis Sandia chemical engineer Nancy Jackson has worked in laboratories around the world to help ensure that chemicals are used safely and kept secure. The American Association for the Advancement of Science honored her with the 2013 Science Diplomacy Award. | Photo by Randy Montoya, Sandia National Lab. Sandia chemical engineer Nancy Jackson has worked in laboratories around the world to help ensure that chemicals are used safely and kept secure. The American Association for the Advancement of Science honored her with the 2013 Science Diplomacy Award. | Photo by Randy Montoya, Sandia National Lab. Stephanie Hobby Media Relations, Sandia National Lab

90

PUREX Plant waste analysis plan. Revision 1  

SciTech Connect (OSTI)

A Washington Administrative Code 173-303-300 requires that a facility shall develop and follow a written analysis plan which describes the procedures that will be followed to ensure that its dangerous wastes are managed properly. This document covers the activities at the PUREX Plant to characterize and designate waste that is generated within the plant and stored in Tanks F18 and U3/U4 prior to transfer to Tank Farms.

Ellis, M.W.

1994-08-15T23:59:59.000Z

91

Waste minimization/pollution prevention study of high-priority waste streams  

SciTech Connect (OSTI)

Although waste minimization has been practiced by the Metals and Ceramics (M&C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division`s pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M&C staff members empowered by the Division Director to study specific waste streams.

Ogle, R.B. [comp.

1994-03-01T23:59:59.000Z

92

Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B  

SciTech Connect (OSTI)

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01T23:59:59.000Z

93

Communicating Dangers and Opportunities in Global Warming 13 December Draft  

E-Print Network [OSTI]

Communicating Dangers and Opportunities in Global Warming 13 December Draft James Hansen American: "Subversion of Public Affairs Chart 7: The Global Warming Story C. Tenets of a Democracy: "An Informed Public, not as a spokesman for NASA There is a huge gap between what is understood about global warming and what is known

Hansen, James E.

94

Sir --Venezuela has entered 2003 deadlocked in a dangerous political  

E-Print Network [OSTI]

Sir -- Venezuela has entered 2003 deadlocked in a dangerous political confrontation and a general to preserve Venezuela's science and its natural environment, which is rich in biodiversity. We ask for Scientific Research, PO Box 21827, Caracas 1020A, Venezuela correspondence NATURE |VOL 421 |30 JANUARY 2003

Chapman, Clark R.

95

Operating Experience Level 3, Losing Control: Material Handling Dangers  

Broader source: Energy.gov [DOE]

This Operating Experience Level 3 (OE-3) document provides information about the dangers inherent in material handling and the role hazard analysis, work planning, and walkdowns can play in preventing injuries during heavy equipment moves. More than 200 material handling events reported to the Occurrence Reporting and Processing System (ORPS) from January 1, 2010, through August 31, 2014.

96

Operating Experience Level 3, Losting Control: Material Handling Dangers  

Broader source: Energy.gov [DOE]

This Operating Experience Level 3 (OE-3) document provides information about the dangers inherent in material handling and the role hazard analysis, work planning, and walkdowns can play in preventing injuries during heavy equipment moves. More than 200 material handling events reported to the Occurrence Reporting and Processing System (ORPS) from January 1, 2010, through August 31, 2014.

97

The Level Paradox of E-Collaboration: Dangers and Solutions  

Science Journals Connector (OSTI)

Although e-collaboration phenomena are multilevel in nature, research to date has been conducted from an exclusively single-level focus. This has lead to the level paradox. The dangers of the level paradox are discussed, including the potential that ... Keywords: Analysis, Bias, Communication Media, Cumulative Knowledge, Mixed-Level, Multilevel, Single-Level, Virtual Team

Ana Ortiz de Guinea

2011-10-01T23:59:59.000Z

98

Risk analysis of buried wastes from electricity generation  

Science Journals Connector (OSTI)

There has been a great deal of public concern about the dangers of buried radioactive waste from the nuclear industry. The rational approach to evaluating these concerns is to develop quantitative estimates of the health impacts to be expected from these wastes and compare them with the health impacts of wastes from alternative technologies. It is our purpose here to outline that process and develop the results.

Bernard L. Cohen

1986-01-01T23:59:59.000Z

99

Operating limit evaluation for disposal of uranium enrichment plant wastes  

SciTech Connect (OSTI)

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) will accept wastes generated during normal plant operations that are considered to be non-radioactive. However, nearly all solid waste from any source or facility contains small amounts of radioactive material, due to the presence in most materials of trace quantities of such naturally occurring radionuclides as uranium and thorium. This paper describes an evaluation of operating limits, which are protective of public health and the environment, that would allow waste materials containing small amounts of radioactive material to be sent to a new solid waste landfill at PGDP. The operating limits are expressed as limits on concentrations of radionuclides in waste materials that could be sent to the landfill based on a site-specific analysis of the performance of the facility. These limits are advantageous to PGDP and DOE for several reasons. Most importantly, substantial cost savings in the management of waste is achieved. In addition, certain liabilities that could result from shipment of wastes to a commercial off-site solid waste landfill are avoided. Finally, assurance that disposal operations at the PGDP landfill are protective of public health and the environment is provided by establishing verifiable operating limits for small amounts of radioactive material; rather than relying solely on administrative controls. The operating limit determined in this study has been presented to the Commonwealth of Kentucky and accepted as a condition to be attached to the operating permit for the solid waste landfill.

Lee, D.W.; Kocher, D.C.; Wang, J.C.

1996-02-01T23:59:59.000Z

100

Molten Salt Oxidation of mixed wastes  

SciTech Connect (OSTI)

Molten Salt Oxidation (MSO) can be characterized as a simple noncombustion process; the basic concept is to introduce air and wastes into a bed of molten salt, oxidize the organic wastes in the molten salt, use the heat of oxidation to keep the salt molten and remove the salt for disposal or processing and recycling. The process has been developed through bench-scale and pilot-scale testing, with successful destruction demonstration of a wide variety of hazardous and mixed (radioactive and hazardous) wastes including chemical warfare agents, combustible solids, halogenated solvents, polychlorinated biphenyls, plutonium-contaminated solids, uranium-contaminated solvents and fission product-contaminated oil. The MSO destruction efficiency of the hazardous organic constituents in the wastes exceeds 99.9999%. Radioactive species, such as actinides and rare earth fission products, are retained in the salt bath. These elements can be recovered from the spent salt using conventional chemical processes, such as ion exchange, to render the salt as nonradioactive and nonhazardous. This paper reviews the principles and capabilities of MSO, previous mixed waste studies, and a new US Department of Energy program to demonstrate the process for the treatment of mixed wastes.

Gay, R.L.; Navratil, J.D.; Newman, C. [Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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.


101

Hanford tank waste simulants specification and their applicability for the retrieval, pretreatment, and vitrification processes  

SciTech Connect (OSTI)

A wide variety of waste simulants were developed over the past few years to test various retrieval, pretreatment and waste immobilization technologies and unit operations. Experiments can be performed cost-effectively using non-radioactive waste simulants in open laboratories. This document reviews the composition of many previously used waste simulants for remediation of tank wastes at the Hanford reservation. In this review, the simulants used in testing for the retrieval, pretreatment, and vitrification processes are compiled, and the representative chemical and physical characteristics of each simulant are specified. The retrieval and transport simulants may be useful for testing in-plant fluidic devices and in some cases for filtration technologies. The pretreatment simulants will be useful for filtration, Sr/TRU removal, and ion exchange testing. The vitrification simulants will be useful for testing melter, melter feed preparation technologies, and for waste form evaluations.

GR Golcar; NG Colton; JG Darab; HD Smith

2000-04-04T23:59:59.000Z

102

The Threat to the Planet: How Can We Avoid Dangerous Human-Made Climate Change?  

E-Print Network [OSTI]

. That is much less than day-to-day weather fluctuations. But another half degree Celsius warming-made climate change, but what level is dangerous? Chart 4. Critical metrics defining dangerous, I believe

Hansen, James E.

103

300 Area waste acid treatment system closure plan  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

LUKE, S.N.

1999-05-17T23:59:59.000Z

104

pilF Polymorphism-Based PCR To Distinguish Vibrio vulnificus Strains Potentially Dangerous to Public Health  

Science Journals Connector (OSTI)

...vulnificus Strains Potentially Dangerous to Public Health Published ahead of print...that could be considered dangerous to public health. Discrimination is based...isolates that potentially are dangerous to public health, under the hypothesis...

Francisco J. Roig; Eva Sanjuán; Amparo Llorens; Carmen Amaro

2009-12-28T23:59:59.000Z

105

A Web-Oriented Geoinformation System Application for Forest Fire Danger Prediction in Typical Forests of the Ukraine  

Science Journals Connector (OSTI)

A web-oriented geoinformation system for forest fire danger prediction based on a probabilistic fire danger criteria is described in this chapter. A new method for determining the probabilistic fire danger cri...

Nikolay Baranovskiy; Marina Zharikova

2014-01-01T23:59:59.000Z

106

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING AS A SUPPLEMENTARY TREATMENT FOR HANFORD'S LOW ACTIVITY WASTE AND SECONDARY WASTES  

SciTech Connect (OSTI)

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the Savannah River National Laboratory (SRNL) to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of I-125/129 and Tc-99 to chemically resemble WTP-SW. Ninety six grams of radioactive product were made for testing. The second campaign commenced using SRS LAW chemically trimmed to look like Hanford's LAW. Six hundred grams of radioactive product were made for extensive testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

2011-02-24T23:59:59.000Z

107

A SLIPPERY SLOPE: HOW MUCH GLOBAL WARMING CONSTITUTES "DANGEROUS ANTHROPOGENIC INTERFERENCE"?  

E-Print Network [OSTI]

A SLIPPERY SLOPE: HOW MUCH GLOBAL WARMING CONSTITUTES "DANGEROUS ANTHROPOGENIC INTERFERENCE on the global warming that can be tolerated without risking dangerous anthropogenic interference with climate. I" mainly as a metaphor for the danger posed by global warming. So I changed "Hell" to "disaster." What

Hansen, James E.

108

Saaremaa Hantavirus Should Not Be Confused with Its Dangerous Relative, Dobrava Virus  

Science Journals Connector (OSTI)

...Should Not Be Confused with Its Dangerous Relative, Dobrava Virus Alexander...known to be one of the most dangerous European viral pathogens...Research Institute for Animal Health Institute for Novel and Emerging...should not be confused with its dangerous relative, Dobrava virus...

Alexander Plyusnin; Antti Vaheri; Åke Lundkvist

2006-04-01T23:59:59.000Z

109

The evolution of cultural adaptations: Fijian food taboos protect against dangerous marine toxins  

Science Journals Connector (OSTI)

...taboos protect against dangerous marine toxins Joseph...V6T 1Z4 3 Centre for Health Evaluation and Outcome...might be a significant health threat. Ciguatera poisoning...most commonly achieving dangerous levels in large, often...on tabooing the most dangerous species, so there is...

2010-01-01T23:59:59.000Z

110

Preventing Buoyant Displacement Gas Release Events in Hanford Double-Shell Waste Tanks  

SciTech Connect (OSTI)

This report summarizes the predictive methods used to ensure that waste transfer operations in Hanford waste tanks do not create waste configurations that lead to unsafe gas release events. The gas release behavior of the waste in existing double-shell tanks has been well characterized, and the flammable gas safety issues associated with safe storage of waste in the current configuration are being formally resolved. However, waste is also being transferred between double-shell tanks and from single-shell tanks into double-shell tanks by saltwell pumping and sluicing that create new wastes and waste configurations that have not been studied as well. Additionally, planning is underway for various waste transfer scenarios to support waste feed delivery to the proposed vitrification plant. It is critical that such waste transfers do not create waste conditions with the potential for dangerous gas release events.

Meyer, Perry A.; Stewart, Charles W.

2001-01-01T23:59:59.000Z

111

Secondary Waste Forms and Technetium Management  

Broader source: Energy.gov (indexed) [DOE]

Secondary Waste Forms and Secondary Waste Forms and Technetium Management Joseph H. Westsik, Jr. Pacific Northwest National Laboratory EM HLW Corporate Board Meeting November 18, 2010 What are Secondary Wastes? Process condensates and scrubber and/or off-gas treatment liquids from the pretreatment and ILAW melter facilities at the Hanford WTP. Sent from WTP to the Effluent Treatment Facility (ETF) for treatment and disposal Treated liquid effluents under the ETF State Wastewater Discharge Permit Solidified liquid effluents under the Dangerous Waste Permit for disposal at the Integrated Disposal Facility (IDF) Solidification Treatment Unit to be added to ETF to provide capacity for WTP secondary liquid wastes 2 Evaporator Condensate Solution Evaporator Pretreatment Melter SBS/ WESP Secondary

112

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

113

Secondary Waste Form Development and Optimization—Cast Stone  

SciTech Connect (OSTI)

Washington River Protection Services is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF is a Resource Conservation and Recovery Act-permitted, multi-waste, treatment and storage unit and can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid wastes generated during operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The STU to ETF will provide the additional capacity needed for ETF to process the increased volume of secondary wastes expected to be produced by WTP.

Sundaram, S. K.; Parker, Kent E.; Valenta, Michelle M.; Pitman, Stan G.; Chun, Jaehun; Chung, Chul-Woo; Kimura, Marcia L.; Burns, Carolyn A.; Um, Wooyong; Westsik, Joseph H.

2011-07-14T23:59:59.000Z

114

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING WITH ACUTAL HANFORD LOW ACTIVITY WASTES VERIFYING FBSR AS A SUPPLEMENTARY TREATMENT  

SciTech Connect (OSTI)

The U.S. Department of Energy's Office of River Protection is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the cleanup mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA). Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. Fluidized Bed Steam Reforming (FBSR) is one of the supplementary treatments being considered. FBSR offers a moderate temperature (700-750 C) continuous method by which LAW and other secondary wastes can be processed irrespective of whether they contain organics, nitrates/nitrites, sulfates/sulfides, chlorides, fluorides, and/or radio-nuclides like I-129 and Tc-99. Radioactive testing of Savannah River LAW (Tank 50) shimmed to resemble Hanford LAW and actual Hanford LAW (SX-105 and AN-103) have produced a ceramic (mineral) waste form which is the same as the non-radioactive waste simulants tested at the engineering scale. The radioactive testing demonstrated that the FBSR process can retain the volatile radioactive components that cannot be contained at vitrification temperatures. The radioactive and nonradioactive mineral waste forms that were produced by co-processing waste with kaolin clay in an FBSR process are shown to be as durable as LAW glass.

Jantzen, C.; Crawford, C.; Burket, P.; Bannochie, C.; Daniel, G.; Nash, C.; Cozzi, A.; Herman, C.

2012-01-12T23:59:59.000Z

115

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...4). Although disposal of HLW remains...for long-term disposal is through deep...successful waste-disposal program has eluded...geologic repository at Yucca Mountain, Nevada. Authorized...Administration withdrew funding for Yucca Mountain...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

116

An Examination of Parents' Influence Strategies on College Students' Dangerous Drinking.  

E-Print Network [OSTI]

??Dangerous drinking on college campuses is a significant public health issue. Over the last decade, the National Institute on Alcohol Abuse and Alcoholism and the… (more)

Menegatos, Lisa Marie

2011-01-01T23:59:59.000Z

117

For Motorcycle Riders Don't place yourself in danger of becoming a statistic  

E-Print Network [OSTI]

For Motorcycle Riders Risks Don't place yourself in danger of becoming a statistic by increasing · Makesureyouhaveasuitableseatfittedonyour motorcycle · Apassengerisyourresponsibility-makesurethey areaswellprotectedasyouare

Tobar, Michael

118

Chapter 6 - Dangerous Herbal Weight-Loss Supplements  

Science Journals Connector (OSTI)

The United States and Mexico are among the most obese nations in the world. Weight-loss supplements containing herbs are popular on both sides of the US/Mexico border, but there is scant information as to their efficacy or safety. Two herbal products have recently been touted as being effective and safe for weight loss: candle nut tree seeds (‘Nuez de la India’) and yellow oleander seed (‘Codo de Fraile’). Both these products are dangerous and have caused serious health problems in various countries. People should be aware not to self-medicate with certain herbal supplements for weight loss. Keywords: Candle nut tree; Codo de Fraile; Complementary and alternative medicine; Herbal supplements; Nuez de la India; Obesity; Toxic plants; Weight loss; Yellow oleander

A. González-Stuart

2013-01-01T23:59:59.000Z

119

New England Wind Forum: Am I in Danger?  

Wind Powering America (EERE)

Am I in Danger? Am I in Danger? With tens of thousands in operation across the world, wind turbines have demonstrated an excellent safety track record. Primary safety issues of concern are the icing of the blades and resulting shedding of the ice and the potential impact of a blade throw. Ice Shedding Under certain conditions in climates such as those found in New England, ice can accumulate on wind turbine blades. The release of that ice from moving turbine blades is possible. (The potential is clearly highest at mountain-top sites, remote from most observers in the harshest of weather.) A wind installation typically addresses such possibilities by employing adequate setbacks between each turbine and any nearby residences to avoid risk. Severe ice buildup will lead to automatic turbine shut down until the condition improves. Modern turbines can be equipped with cold weather packages, which make them adaptable to temperatures as low as -40 Celsius, reducing the risk of ice accumulation. These packages include special coatings on the blades to eliminate the adherence of ice, thermostat-controlled resistive element forced air heaters strategically placed to heat instruments and operating components during cold weather conditions to prevent the formation and adherence of ice, and low-temperature lubricants. No studies have been conducted in the United States concerning ice shedding from wind turbine blades. The 1998 European study, "Assessment of Safety Risks Arising from Wind Turbine Icing" (PDF 57 KB) Download Adobe Reader by European Commission, DGXII, and the UK Department of Trade and Industry examines the issue as well as the study "Risk Analysis of Ice Throw From Wind Turbines" (PDF 297 KB) Download Adobe Reader presented in April 2003 at BOREAS conference in Finland.

120

Stabilization of Savannah River National Laboartory (SRNL) Aqueous Waste by Fluidized Bed Steam Reforming (FBSR)  

SciTech Connect (OSTI)

The Savannah River National Laboratory (SRNL) is a multidisciplinary laboratory operated by Westinghouse Savannah River Company (WSRC) in Aiken, South Carolina. Research and development programs have been conducted at SRNL for {approx}50 years generating non-radioactive (hazardous and non-hazardous) and radioactive aqueous wastes. Typically the aqueous effluents from the R&D activities are disposed of from each laboratory module via the High Activity Drains (HAD) or the Low Activity Drains (LAD) depending on whether they are radioactive or not. The aqueous effluents are collected in holding tanks, analyzed and shipped to either H-Area (HAD waste) or the F/H Area Effluent Treatment Facility (ETF) (LAD waste) for volume reduction. Because collection, analysis, and transport of LAD and HAD waste is cumbersome and since future treatment of this waste may be curtailed as the F/H-Area evaporators and waste tanks are decommissioned, SRNL laboratory operations requested several proof of principle demonstrations of alternate technologies that would define an alternative disposal path for the aqueous wastes. Proof of principle for the disposal of SRNL HAD waste using a technology known as Fluidized Bed Steam Reforming (FBSR) is the focus of the current study. The FBSR technology can be performed either as a batch process, e.g. in each laboratory module in small furnaces with an 8'' by 8'' footprint, or in a semi-continuous Bench Scale Reformer (BSR). The proof of principle experiments described in this study cover the use of the FBSR technology at any scale (pilot or full scale). The proof of principle experiments described in this study used a non-radioactive HAD simulant.

Jantzen, C

2004-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Operating limit study for the proposed solid waste landfill at Paducah Gaseous Diffusion Plant  

SciTech Connect (OSTI)

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) would accept wastes generated during normal operations that are identified as non-radioactive. These wastes may include small amounts of radioactive material from incidental contamination during plant operations. A site-specific analysis of the new solid waste landfill is presented to determine a proposed operating limit that will allow for waste disposal operations to occur such that protection of public health and the environment from the presence of incidentally contaminated waste materials can be assured. Performance objectives for disposal were defined from existing regulatory guidance to establish reasonable dose limits for protection of public health and the environment. Waste concentration limits were determined consistent with these performance objectives for the protection of off-site individuals and inadvertent intruders who might be directly exposed to disposed wastes. Exposures of off-site individuals were estimated using a conservative, site-specific model of the groundwater transport of contamination from the wastes. Direct intrusion was analyzed using an agricultural homesteader scenario. The most limiting concentrations from direct intrusion or groundwater transport were used to establish the concentration limits for radionuclides likely to be present in PGDP wastes.

Lee, D.W.; Wang, J.C.; Kocher, D.C.

1995-06-01T23:59:59.000Z

122

THE RISK OF NUCLEAR TERRORISM AND NEXT STEPS TO REDUCE THE DANGER  

E-Print Network [OSTI]

THE RISK OF NUCLEAR TERRORISM ­ AND NEXT STEPS TO REDUCE THE DANGER TESTIMONY OF MATTHEW BUNN urgent threats to America's security ­ the threat of nuclear terrorism. My message to you today is simple, "The Risk of Nuclear Terrorism ­ And Next Steps to Reduce the Danger," April 2, 2008 2 Nuclear

Laughlin, Robert B.

123

USDA Forest Service Gen. Tech. Rep. PSW-GTR-181. 2002. 863 British Columbia's Dangerous Tree  

E-Print Network [OSTI]

USDA Forest Service Gen. Tech. Rep. PSW-GTR-181. 2002. 863 British Columbia's Dangerous Tree Guy7 Abstract New dangerous tree assessment guidelines have recently been developed by the Wildlife or dying tree over 3 meters in height." New Workers' Compensation Board Occupational Health and Safety

Standiford, Richard B.

124

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot  

SciTech Connect (OSTI)

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ``near-reference`` with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed.

Molecke, M.A.; Argueello, G.J.; Beraun, R.

1993-04-01T23:59:59.000Z

125

Estimating Waste Inventory and Waste Tank Characterization |...  

Office of Environmental Management (EM)

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

126

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a “nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

127

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network [OSTI]

waste (i.e, mixture of biohazardous and chemical or radioactive waste), call Environment, Health2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619

Tsien, Roger Y.

128

Dangerous and severe personality disorder: An investigation of the construct  

Science Journals Connector (OSTI)

Introduction of the construct “Dangerous and Severe Personality Disorder” (DSPD) by the UK Home Office and Department of Health has provoked strong debate and opposition. Its aims and that of proposed subsequent legislation was to enhance public protection by identifying and detaining a minority of persons with severe personality disorder who pose a high risk of serious sexual/violent offending. The most serious criticism was the ethical implication of allowing indefinite detention of people without criminal convictions. More recently, policy emphasis has shifted towards treatment. 1396 male prisoners serving sentences of 2+ years for sexual/violent offenses were prospectively interviewed (personality disorders, psychopathy, and risk) at a mean follow-up of 2 years. The prevalence of DSPD was 15%. Significantly more re-offended. Five DSPD offenders would need treatment to prevent one violent act. Based on an estimate of attributable risk, successful treatment of DSPD could reduce violent re-convictions among DSPD offenders by 71% and violent/sexual re-offenses in the prison population by 27%. DSPD criteria correctly identify high risk prisoners but primarily through risk-related demographic features. DSPD does not accurately identify serious sexual/violent re-offenders. The DSPD programme may reduce major violent re-offending if treatment interventions prove effective.

Simone Ullrich; Min Yang; Jeremy Coid

2010-01-01T23:59:59.000Z

129

Simulated Waste Testing Of Glycolate Impacts On The 2H-Evaporator System  

SciTech Connect (OSTI)

Glycolic acid is being studied as a total or partial replacement for formic acid in the Defense Waste Processing Facility (DWPF) feed preparation process. After implementation, the recycle stream from DWPF back to the high-level waste tank farm will contain soluble sodium glycolate. Most of the potential impacts of glycolate in the tank farm were addressed via a literature review, but several outstanding issues remained. This report documents the non-radioactive simulant tests impacts of glycolate on storage and evaporation of Savannah River Site high-level waste. The testing for which non-radioactive simulants could be used involved the following: the partitioning of glycolate into the evaporator condensate, the impacts of glycolate on metal solubility, and the impacts of glycolate on the formation and dissolution of sodium aluminosilicate scale within the evaporator. The following are among the conclusions from this work: Evaporator condensate did not contain appreciable amounts of glycolate anion. Of all tests, the highest glycolate concentration in the evaporator condensate was 0.38 mg/L. A significant portion of the tests had glycolate concentration in the condensate at less than the limit of quantification (0.1 mg/L). At ambient conditions, evaporator testing did not show significant effects of glycolate on the soluble components in the evaporator concentrates. Testing with sodalite solids and silicon containing solutions did not show significant effects of glycolate on sodium aluminosilicate formation or dissolution.

Martino, C. J.

2013-08-13T23:59:59.000Z

130

Recycle of Zirconium from Used Nuclear Fuel Cladding: A Major Element of Waste Reduction  

SciTech Connect (OSTI)

Feasibility tests were initiated to determine if the zirconium in commercial used nuclear fuel (UNF) cladding can be recovered in sufficient purity to permit re-use, and if the recovery process can be operated economically. Initial tests are being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery process and determine the degree of purification that can be obtained. Early results indicate that quantitative recovery can be accomplished and product contamination with alloy constituents can be controlled sufficiently to meet purification requirements. Future tests with actual radioactive UNF cladding are planned. The objective of current research is to determine the feasibility of recovery and recycle of zirconium from used fuel cladding wastes. Zircaloy cladding, which contains 98+% of hafnium-free zirconium, is the second largest mass, on average {approx}25 wt %, of the components in used U.S. light-water-reactor fuel assemblies. Therefore, recovery and recycle of the zirconium would enable a large reduction in geologic waste disposal for advanced fuel cycles. Current practice is to compact or grout the cladding waste and store it for subsequent disposal in a geologic repository. This paper describes results of initial tests being performed with unirradiated, non-radioactive samples of various types of Zircaloy materials that are used in UNF cladding to develop the recovery process and determine the degree of purification that can be obtained. Future tests with actual radioactive UNF cladding are planned.

Collins, Emory D [ORNL; DelCul, Guillermo D [ORNL; Terekhov, Dmitri [ORNL; Emmanuel, N. V. [Chemical Vapor Metal Refining, Inc.

2011-01-01T23:59:59.000Z

131

DEVELOPMENT OF A KINETIC MODEL OF BOEHMITE DISSOLUTION IN CAUSTIC SOLUTIONS APPLIED TO OPTIMIZE HANFORD WASTE PROCESSING  

SciTech Connect (OSTI)

Boehmite (e.g., aluminum oxyhydroxide) is a major non-radioactive component in Hanford and Savannah River nuclear tank waste sludge. Boehmite dissolution from sludge using caustic at elevated temperatures is being planned at Hanford to minimize the mass of material disposed of as high-level waste (HLW) during operation of the Waste Treatment Plant (WTP). To more thoroughly understand the chemistry of this dissolution process, we have developed an empirical kinetic model for aluminate production due to boehmite dissolution. Application of this model to Hanford tank wastes would allow predictability and optimization of the caustic leaching of aluminum solids, potentially yielding significant improvements to overall processing time, disposal cost, and schedule. This report presents an empirical kinetic model that can be used to estimate the aluminate production from the leaching of boehmite in Hanford waste as a function of the following parameters: (1) hydroxide concentration; (2) temperature; (3) specific surface area of boehmite; (4) initial soluble aluminate plus gibbsite present in waste; (5) concentration of boehmite in the waste; and (6) (pre-fit) Arrhenius kinetic parameters. The model was fit to laboratory, non-radioactive (e.g. 'simulant boehmite') leaching results, providing best-fit values of the Arrhenius A-factor, A, and apparent activation energy, E{sub A}, of A = 5.0 x 10{sup 12} hour{sup -1} and E{sub A} = 90 kJ/mole. These parameters were then used to predict boehmite leaching behavior observed in previously reported actual waste leaching studies. Acceptable aluminate versus leaching time profiles were predicted for waste leaching data from both Hanford and Savannah River site studies.

DISSELKAMP RS

2011-01-06T23:59:59.000Z

132

Summary of available waste forecast data for the Environmental Restoration Program at the Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This report identifies patterns of Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) waste generation that are predicted by the current ER Waste Generation Forecast data base. It compares the waste volumes to be generated with the waste management capabilities of current and proposed treatment, storage, or disposal (TSD) facilities. The scope of this report is limited to wastes generated during activities funded by the Office of the Deputy Assistant Secretary for Environmental Restoration (EM-40) and excludes wastes from the decontamination and decommissioning of facilities. Significant quantities of these wastes are expected to be generated during ER activities. This report has been developed as a management tool supporting communication and coordination of waste management activities at ORNL. It summarizes the available data for waste that will be generated as a result of remediation activities under the direction of the U.S. Department of Energy Oak Ridge Operations Office and identifies areas requiring continued waste management planning and coordination. Based on the available data, it is evident that most remedial action wastes leaving the area of contamination can be managed adequately with existing and planned ORR waste management facilities if attention is given to waste generation scheduling and the physical limitations of particular TSD facilities. Limited use of off-site commercial TSD facilities is anticipated, provided the affected waste streams can be shown to satisfy the requirements of the performance objective for certification of non-radioactive hazardous waste and the waste acceptance criteria of the off-site facilities. Ongoing waste characterization will be required to determine the most appropriate TSD facility for each waste stream.

Not Available

1994-08-01T23:59:59.000Z

133

Hanford high-level waste evaporator/crystallizer corrosion evaluation  

SciTech Connect (OSTI)

The US Department of Energy, Hanford Site nuclear reservation, located in Southeastern Washington State, is currently home to 61 Mgal of radioactive waste stored in 177 large underground storage tanks. As an intermediate waste volume reduction, the 242-A Evaporator/Crystallizer processes waste solutions from most of the operating laboratories and plants on the Hanford Site. The waste solutions are concentrated in the Evaporator/Crystallizer to a slurry of liquid and crystallized salts. This concentrated slurry is returned to Hanford Site waste tanks at a significantly reduced volume. The Washington State Department of Ecology Dangerous Waste Regulations, WAC 173-393 require that a tank system integrity assessment be completed and maintained on file at the facility for all dangerous waste tank systems. This corrosion evaluation was performed in support of the 242-A Evaporator/Crystallizer Tank System Integrity Assessment Report. This corrosion evaluation provided a comprehensive compatibility study of the component materials and corrosive environments. Materials used for the Evaporator components and piping include austenitic stainless steels (SS) (primarily ASTM A240, Type 304L) and low alloy carbon steels (CS) (primarily ASTM A53 and A106) with polymeric or asbestos gaskets at flanged connections. Building structure and secondary containment is made from ACI 301-72 Structural Concrete for Buildings and coated with a chemically resistant acrylic coating system.

Ohl, P.C.; Carlos, W.C.

1993-10-01T23:59:59.000Z

134

To state the policy of LSU regarding the possession of firearms and dangerous weapons within its facilities and premises and  

E-Print Network [OSTI]

PURPOSE To state the policy of LSU regarding the possession of firearms and dangerous weapons other firearm from which a shot or shots are discharged by an explosive. Dangerous Weapons. Any gas, LSU prohibits the possession of firearms or other dangerous weapons within the campus residences

Harms, Kyle E.

135

P:\\Policy & Procedures\\EHS\\EH&S#16-Receiving dangerous goods-rev.doc Environmental Health & Safety  

E-Print Network [OSTI]

P:\\Policy & Procedures\\EHS\\EH&S#16-Receiving dangerous goods-rev.doc Environmental Health & Safety. ENVIRONMENTAL HEALTH AND SAFETY Provide training concerning procedures for accepting and recognizing dangerous Policy & Procedure #16 TITLE: DANGEROUS GOODS RECEIVING POLICY OBJECTIVE AND PURPOSE: To ensure packages

Fernandez, Eduardo

136

Network-centric Warfare and the Globalization of Technology: Transforming simple tools into dangerous weapons  

E-Print Network [OSTI]

tools into dangerous weapons New applications of technology,made bombs are primary weapons for suicide also “flattened”in com- devices, and weapons to utilize in guerilla warfare.

Oh, Ann

2009-01-01T23:59:59.000Z

137

CHARACTERIZING DANGEROUS WAVES FOR OCEAN WAVE ENERGY CONVERTER SURVIVABILITY Justin Hovland  

E-Print Network [OSTI]

CHARACTERIZING DANGEROUS WAVES FOR OCEAN WAVE ENERGY CONVERTER SURVIVABILITY Justin Hovland ABSTRACT Ocean Wave Energy Converters (OWECs) operating on the water surface are subject to storms at station 139. Keywords: wave energy, survivability, breaking waves, joint distribution, OWEC INTRODUCTION

Haller, Merrick

138

Operating Experience Level 3, Dangers of Objects Falling into Normally Occupied Areas  

Broader source: Energy.gov [DOE]

This Operating Experience Level 3 (OE-3) document provides information about a safety concern related to the dangers of items falling from heights into spaces normally occupied by workers at Department of Energy (DOE) facilities.

139

Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan  

SciTech Connect (OSTI)

This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

SIMMONS, F.M.

2000-12-01T23:59:59.000Z

140

Organic Tanks Safety Program: Waste aging studies  

SciTech Connect (OSTI)

The underground storage tanks at the Hanford Complex contain wastes generated from many years of plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct on several specific safety issues, including potential energy releases from these tanks. This report details the first year`s findings of a study charged with determining how thermal and radiological processes may change the composition of organic compounds disposed to the tank. Their approach relies on literature precedent, experiments with simulated waste, and studies of model reactions. During the past year, efforts have focused on the global reaction kinetics of a simulated waste exposed to {gamma} radiation, the reactions of organic radicals with nitrite ion, and the decomposition reactions of nitro compounds. In experiments with an organic tank non-radioactive simulant, the authors found that gas production is predominantly radiolytically induced. Concurrent with gas generation they observe the disappearance of EDTA, TBP, DBP and hexone. In the absence of radiolysis, the TBP readily saponifies in the basic medium, but decomposition of the other compounds required radiolysis. Key organic intermediates in the model are C-N bonded compounds such as oximes. As discussed in the report, oximes and nitro compounds decompose in strong base to yield aldehydes, ketones and carboxylic acids (from nitriles). Certain aldehydes can react in the absence of radiolysis to form H{sub 2}. Thus, if the pathways are correct, then organic compounds reacting via these pathways are oxidizing to lower energy content. 75 refs.

Camaioni, D.M.; Samuels, W.D.; Lenihan, B.D.; Clauss, S.A.; Wahl, K.L.; Campbell, J.A.

1994-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

1997 Hanford site report on land disposal restrictions for mixed waste  

SciTech Connect (OSTI)

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

Black, D.G.

1997-04-07T23:59:59.000Z

142

Reference Alloy Waste Form Fabrication and Initiation of Reducing Atmosphere and Reductive Additives Study on Alloy Waste Form Fabrication  

SciTech Connect (OSTI)

This report describes the fabrication of two reference alloy waste forms, RAW-1(Re) and RAW-(Tc) using an optimized loading and heating method. The composition of the alloy materials was based on a generalized formulation to process various proposed feed streams resulting from the processing of used fuel. Waste elements are introduced into molten steel during alloy fabrication and, upon solidification, become incorporated into durable iron-based intermetallic phases of the alloy waste form. The first alloy ingot contained surrogate (non-radioactive), transition-metal fission products with rhenium acting as a surrogate for technetium. The second alloy ingot contained the same components as the first ingot, but included radioactive Tc-99 instead of rhenium. Understanding technetium behavior in the waste form is of particular importance due the longevity of Tc-99 and its mobility in the biosphere in the oxide form. RAW-1(Re) and RAW-1(Tc) are currently being used as test specimens in the comprehensive testing program investigating the corrosion and radionuclide release mechanisms of the representative alloy waste form. Also described in this report is the experimental plan to study the effects of reducing atmospheres and reducing additives to the alloy material during fabrication in an attempt to maximize the oxide content of waste streams that can be accommodated in the alloy waste form. Activities described in the experimental plan will be performed in FY12. The first aspect of the experimental plan is to study oxide formation on the alloy by introducing O2 impurities in the melt cover gas or from added oxide impurities in the feed materials. Reducing atmospheres will then be introduced to the melt cover gas in an attempt to minimize oxide formation during alloy fabrication. The second phase of the experimental plan is to investigate melting parameters associated with alloy fabrication to allow the separation of slag and alloy components of the melt.

S.M. Frank; T.P. O'Holleran; P.A. Hahn

2011-09-01T23:59:59.000Z

143

PNNL-20162  

Broader source: Energy.gov (indexed) [DOE]

162 162 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Cultural Resources Review for Closure of the Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill in the 600 Area, Hanford Site, Benton County, Washington - HCRC# 2010-600-018R JL Gutzeit JJ Sharpe EP Kennedy R DeMaris BN Bjornstad M Venno MS Sackschewsky JR Christensen February 2011 DOE/EA-1707D REVISED PREDECISIONAL DRAFT A-1 AUGUST 2011 OFFICIAL USE ONLY 1.0 DOE/EA-1707D REVISED PREDECISIONAL DRAFT A-2 AUGUST 2011 PNNL-20162 Cultural Resources Review for Closure of the Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill in the 600 Area, Hanford Site, Benton County, Washington - HCRC# 2010-600-018R JL Gutzeit JJ Sharpe 1 EP Kennedy R DeMaris

144

Slide 1  

Broader source: Energy.gov (indexed) [DOE]

Environmental Assessment for Closing Hanford's Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill The U.S. Department of Energy (DOE) is issuing a National Environmental Policy Act of 1969 (NEPA) revised draft environmental assessment (EA). The revised draft EA evaluates the potential environmental impacts of closing the Nonradioactive Dangerous Waste Landfill and Solid Waste Landfill. We welcome your comments and suggestions. The Washington State Department of Ecology (Ecology) is a cooperating agency on this revised draft EA. What do I need to know about this study? This document addresses and incorporates comments from the 30-day (with a 30-day extension) public comment period held in May 2010 for a draft environmental assessment for

145

242-A Evaporator Waste Analysis Plan. Revision 5  

SciTech Connect (OSTI)

This Waste Analysis Plan (WAP) provides the plan for obtaining information needed for proper waste handling and processing in the 242-A Evaporator (Evaporator) located on the Hanford Site. In particular it addresses analysis necessary to manage the waste according to Washington Administrative Code (WAC) 173-303 and Parts 264 and 265 of the Code of Federal Regulations (CFR). Regulatory and safety issues are addressed by establishing boundary conditions for waste received and treated at the 242-A Evaporator. The boundary conditions are set by establishing limits for items such as potential exothermic reactions, waste compatibility, and control of vessel vent organic emissions. Boundary conditions are also set for operational considerations and to ensure waste acceptance at receiving facilities. The issues that are addressed in this plan include prevention of exotherms in the waste, waste compatibility, and vessel vent emissions. Samples from the other streams associated with the Evaporator are taken as required by Process Control Plans but are excluded from this plan because either the streams do not contain dangerous waste or the analyses are not required by WAC 173-303-300.

Basra, T.S.

1995-04-13T23:59:59.000Z

146

Microsoft Word - CX-Bonneville-HoodRiverDangerPoleandARFY12_WEB.docx  

Broader source: Energy.gov (indexed) [DOE]

September 14, 2012 REPLY TO ATTN OF: KEP-4 SUBJECT: Environmental Clearance Memorandum Darin Bowman Civil Engineer - TELF-TPP-3 Proposed Action: Bonneville-Hood River No. 1 Danger Pole Replacement and Access Road Upgrades Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021): B1.3, Routine Maintenance Location: Hood River County, OR Proposed by: Bonneville Power Administration (BPA) Description of the Proposed Action: Upgrade access roads and landings from Structures 6/1 through 7/4 and replace danger poles on the Bonneville-Hood River No. 1 115-kV transmission line. Background This project entails improving the existing access along the Bonneville-Hood River No. 1 transmission line; maintaining existing structure landings; and replacing three danger poles and associated hardware.

147

Waste minimization at a plutonium processing facility  

SciTech Connect (OSTI)

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

148

Separation of technetium from nuclear waste stream simulants. Final report  

SciTech Connect (OSTI)

The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

1995-09-11T23:59:59.000Z

149

Waste Hoist  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Primary Hoist: 45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton...

150

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

151

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE (WTP-SW) BY FLUIDIZED BED STEAM REFORMING (FBSR) USING THE BENCH SCALE REFORMER PLATFORM  

SciTech Connect (OSTI)

The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150°C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750°C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford’s WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing. The granular products (both simulant and radioactive) were tested and a subset of the granular material (both simulant and radioactive) were stabilized in a geopolymer matrix. Extensive testing and characterization of the granular and monolith material were made including the following: ? ASTM C1285 (Product Consistency Test) testing of granular and monolith; ? ASTM C1308 accelerated leach testing of the radioactive monolith; ? ASTM C192 compression testing of monoliths; and ? EPA Method 1311 Toxicity Characteristic Leaching Procedure (TCLP) testing. The significant findings of the testing completed on simulant and radioactive WTP-SW are given below: ? Data indicates {sup 99}Tc, Re, Cs, and I

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, G.; Jantzen, C.; Missimer, D.

2014-08-21T23:59:59.000Z

152

Radioactive Demonstration Of Mineralized Waste Forms Made From Hanford Low Activity Waste (Tank SX-105 And AN-103) By Fluidized Bed Steam Reformation  

SciTech Connect (OSTI)

One of the immobilization technologies under consideration as a Supplemental Treatment for Hanford’s Low Activity Waste (LAW) is Fluidized Bed Steam Reforming (FBSR). The FBSR technology forms a mineral waste form at moderate processing temperatures thus retaining and atomically bonding the halides, sulfates, and technetium in the mineral phases (nepheline, sodalite, nosean, carnegieite). Additions of kaolin clay are used instead of glass formers and the minerals formed by the FBSR technology offers (1) atomic bonding of the radionuclides and constituents of concern (COC) comparable to glass, (2) short and long term durability comparable to glass, (3) disposal volumes comparable to glass, and (4) higher Na2O and SO{sub 4} waste loadings than glass. The higher FBSR Na{sub 2}O and SO{sub 4} waste loadings contribute to the low disposal volumes but also provide for more rapid processing of the LAW. Recent FBSR processing and testing of Hanford radioactive LAW (Tank SX-105 and AN-103) waste is reported and compared to previous radioactive and non-radioactive LAW processing and testing.

Jantzen, Carol; Herman, Connie; Crawford, Charles; Bannochie, Christopher; Burket, Paul; Daniel, Gene; Cozzi, Alex; Nash, Charles; Miller, Donald; Missimer, David

2014-01-10T23:59:59.000Z

153

Map Construction and Exploration by Mobile Agents Scattered in a Dangerous Network  

E-Print Network [OSTI]

of routing tables, etc. Underlying many of these tasks is the primitive process of exploration of the networkMap Construction and Exploration by Mobile Agents Scattered in a Dangerous Network Paola Flocchini the exploration and map construction problems. The end result is also a rooted spanning tree and the election

Santoro, Nicola

154

What should we do about the dangers posed by global warming? Judging by  

E-Print Network [OSTI]

What should we do about the dangers posed by global warming? Judging by the collective actions rainandozonedepletioninanattempt toconfusethepublicaboutthescience of global warming and delay regula- tion of greenhouse of Engineering,itdiffersfromtheothers in its attitude towards those who deny the reality of global warming, or hu

Robock, Alan

155

Workplace Violence Prevention Policy Threats at imminent violence, violent incidents, or dangerous or emergency  

E-Print Network [OSTI]

Workplace Violence Prevention Policy Threats at imminent violence, violent incidents, or dangerous and staff, employees, students and visitors. Violent behavior, threats of violence, or physical intimidation of threatening or violent conduct in the workplace, or who observes such behavior or believes a credible threat

Goldberg, Bennett

156

WASTE TO WATTS Waste is a Resource!  

E-Print Network [OSTI]

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From Waste to Energy To Energy from Waste #12;9.00-9.30: Registration 9.30-9.40: Chairman Ella Stengler opens

Columbia University

157

Tradeoffs between food abundance and predation danger in spatial usage of a stopover site by western sandpipers, Calidris mauri  

E-Print Network [OSTI]

Tradeoffs between food abundance and predation danger in spatial usage of a stopover site and predation danger in spatial usage of a stopover site by western sandpipers, Calidris mauri. Á/ Oikos 112. While foraging, animals should alter usage within or between sites to balance the benefits of feeding

158

The Second Opening of the Waste Isolation Pilot Plant? Review of Salient Characteristics and Unique Operational Considerations for Remote Handled Transuranic Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) intends to dispose of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) beginning in 2005. (1) Four principle regulatory agencies are involved in the process of approving the RH TRU waste activities. The DOE is responsible for operational activities. The U. S. Nuclear Regulatory Commission (NRC) approves the design and use of shipping containers. The U.S. Environmental Protection Agency (EPA) is responsible for assuring safe and environmentally effective long-term disposal of the radioactive component of the waste and operational environmental monitoring. The New Mexico Environment Department (NMED) is responsible for the handling and the disposal of the non-radioactive hazardous component of the waste. The Environmental Evaluation Group (EEG) is responsible for performing independent technical oversight of all WIPP activities, and will comment on documents and practices for the various regulated RH TRU waste activities. The DOE has already obtained the necessary approvals from the NRC, and has submitted a Class 3 Modification request to the NMED. On December 16, 2002 the DOE Carlsbad Field Office (CBFO) provided the EPA with a notice of proposed change, in accordance with 40 CFR 194.4 (b) (3), to receive and dispose of remote handled transuranic waste. (2) WIPP procedures for the management of RH TRU waste at the site are being developed. While there are no issues with current NRC Certificates of Compliance for the RH TRU waste shipping containers, it is likely that there will be some controversy over other aspects of the currently planned RH TRU waste program. These issues may include: (1) the published RH TRU waste inventory, (2) the characterization of the radionuclide portion of the waste, for which one planned method is to use dose-to-Curie conversions, and (3) the plans to use bounding estimates for the hazardous portion of the WIPP waste, rather than measuring VOCs on a container-by-container basis or by representative sampling as is done for contact handled transuranic (CH TRU) waste. This paper discusses the currently planned process and the possible issues related to the DOE's efforts to dispose RH TRU waste at the WIPP.

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

159

Repackaging Rocky Flats Legacy Transuranic Waste  

SciTech Connect (OSTI)

Repackaging legacy Transuranic (TRU), Transuranic Mixed (TRM), Low Level Waste (LLW), and Low Level Mixed (LLM) waste requires good characterization skills and the ability to adapt to less than ideal conditions. Repackaging legacy waste in a facility that is not undergoing Decontamination and Decommission (D and D) is optimum. However, repackaging any waste in a D and D facility, under cold and dark conditions, can be difficult. Cold and dark conditions are when the heating and air conditioning are no longer in service and the lighting consists of strands of lights hung throughout each of the rooms. Working under these conditions adds an additional level of stress and danger that must be addressed. The use of glovebags was very useful at Rocky Flats during the D and D of many buildings. Glovebags can be adapted for many different types of wastes and unusual conditions. Repackaging of legacy TRU waste, in a D and D facility, can be accomplished safely and cost effectively with the use of glovebags. In conclusion: the use of glovebags to repackage legacy TRU, TRM, LLW, or LLM waste was done safely and cost effectively at Rocky Flats. The cost of using glovebags was minimal. Glovebags are easily adaptable to whatever the waste configuration is. The use of glovebags, for repackaging of Legacy waste, allows D and D efforts to stay on schedule and on task. Without the use of glovebags, additional gloveboxes would have been required at Rocky Flats. Larger items, such as the HEPA filters, would have required the construction of a new large item repackaging glovebox. Repackaging in glovebags allows the freedom to either locate the glovebag by the waste or locate the glovebag in a place that least impacts D and D efforts. The use of glovebags allowed numerous configurations of waste to be repackaged without the use of gloveboxes. During the D and D of the Rocky Flats facility, which was in a cold and dark stage, D and D work was not impacted by the repackaging activity. Glovebags work well in facilities that are in the process of D and D or still in full operations because glovebags are very safe and cost effective.

McTaggart, Jerri Lynne [Los Alamos National Laboratory, 115 N. Main St., Carlsbad, New Mexico, 88220 (United States)

2008-01-15T23:59:59.000Z

160

Waste Disposal (Illinois)  

Broader source: Energy.gov [DOE]

This article lays an outline of waste disposal regulations, permits and fees, hazardous waste management and underground storage tank requirements.

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Remaining Sites Verification Package for the 128-F-2, 100-F Burning Pit Waste Site, Waste Site Reclassification Form 2008-031  

SciTech Connect (OSTI)

The 128-F-2 waste site consisted of multiple burn and debris filled pits located directly east of the 107-F Retention Basin and approximately 30.5 m east of the northeast corner of the 100-F Area perimeter road that runs along the riverbank. The burn pits were used for incinerating nonradioactive, combustible materials from 1945 to 1965. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

J. M. Capron

2008-12-01T23:59:59.000Z

162

Evaluation of the transport and resuspension of a simulated nuclear waste slurry: Nuclear Waste Treatment Program  

SciTech Connect (OSTI)

The Department of Chemical Engineering at the University of Idaho conducted research on the transport and resuspension of a simulated high-level nuclear waste slurry. In the United States, the reference process for treating both defense and civilian HLLW is vitrification using the liquid-fed ceramic melter process. The non-Newtonian behavior of the slurry complicates the evaluation of the transport and resuspension characteristics of the slurry. The resuspension of a simulated (nonradioactive) melter feed slurry was evaluated using a slurry designated as WV-205. The simulated slurry was developed for the West Valley Demonstration Project and was used during a pilot-scale ceramic melter (PSCM) experiment conducted at PNL in July 1985 (PSCM-21). This study involved determining the transport characteristics of a fully suspended slurry and the resuspension characteristics of settled solids in a pilot-scale pipe loop. The goal was to predict the transport and resuspension of a full-scale system based on rheological data for a specific slurry. The rheological behavior of the slurry was evaluated using a concentric cylinder rotational viscometer, a capillary tube viscometer, and the pilot-scale pipe loop. The results obtained from the three approaches were compared. 40 refs., 74 figs., 15 tabs.

Carleson, T.E.; Drown, D.C.; Hart, R.E.; Peterson, M.E.

1987-09-01T23:59:59.000Z

163

Integrity assessment plan for PNL 300 area radioactive hazardous waste tank system. Final report  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory (PNL), operated by Battelle Memorial Institute under contract to the U.S. Department of Energy, operates tank systems for the U.S. Department of Energy, Richland Operations Office (DOE-RL), that contain dangerous waste constituents as defined by Washington State Department of Ecology (WDOE) Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-040(18). Chapter 173-303-640(2) of the WAC requires the performance of integrity assessments for each existing tank system that treats or stores dangerous waste, except those operating under interim status with compliant secondary containment. This Integrity Assessment Plan (IAP) identifies all tasks that will be performed during the integrity assessment of the PNL-operated Radioactive Liquid Waste Systems (RLWS) associated with the 324 and 325 Buildings located in the 300 Area of the Hanford Site. It describes the inspections, tests, and analyses required to assess the integrity of the PNL RLWS (tanks, ancillary equipment, and secondary containment) and provides sufficient information for adequate budgeting and control of the assessment program. It also provides necessary information to permit the Independent, Qualified, Registered Professional Engineer (IQRPE) to approve the integrity assessment program.

NONE

1996-03-01T23:59:59.000Z

164

Hanford land disposal restrictions plan for mixed wastes  

SciTech Connect (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

165

1998 report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect (OSTI)

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities stored, generation rates, location and method of storage, an assessment of storage-unit compliance status, storage capacity, and the bases and assumptions used in making the estimates.

Black, D.G.

1998-04-10T23:59:59.000Z

166

Worst-Case" Simulant for INTEC Soduim-Bearing Waste Vitrification Tests  

SciTech Connect (OSTI)

The Idaho Nuclear Technology and Engineering Center (INTEC) is developing technologies to process the radioactive liquid sodium-bearing waste from the waste tanks at INTEC to solidify the waste into a form suitable for disposition in a National high-level waste repository currently being considered at Yucca Mountain, Nevada. The requirement is for a qualified glass waste form. Therefore, vitrification is being developed using laboratory, research-scale, and pilot scale melters. While some laboratory experiments can be done with actual waste, the larger scale and most laboratory experiments must be done on non-radioactive simulant waste solutions. Some tests have previously been done on simulants of a representative waste that has been concentrated and will remain unchanged in tank WM-180 until it is vitrified. However, there is a need to develop glass compositions that will accommodate all future wastes in the tanks. Estimates of those future waste compositions have been used along with current compositions to develop a “worst-case” waste composition and a simulant preparation recipe suitable for developing a bracketing glass formulation and for characterizing the flowpath and decontamination factors of pertinent off-gas constituents in the vitrification process. The considerations include development of criteria for a worst-case composition. In developing the criteria, the species that are known to affect vitrification and glass properties were considered. Specific components that may need to be characterized in the off-gas cleanup system were considered in relation to detection limits that would need to be exceeded in order to track those components. Chemical aspects of various constituent interactions that should be taken into account when a component may need to be increased in concentration from that in the actual waste for detection in experiments were evaluated. The worst-case waste simulant composition is comprised of the highest concentration of each species of concern that will be present in current and future wastes from different tanks. Because most of the species of concern are at small concentrations relative to the bulk components that are fairly constant, maximizing them individually into a single waste composition does not substantially affect the general vitrification chemistry. The evaluation and results are reported here. This simulant is suitable for performing laboratory and pilot-scale tests in order to develop the vitrification technology.

Christian, Jerry Dale; Batcheller, Thomas Aquinas

2001-09-01T23:59:59.000Z

167

The IFR pyroprocessing for high-level waste minimization  

SciTech Connect (OSTI)

The process developed for the recycle of integral fast reactor (IFR) spent fuel utilizes a combination of pyrometallurgical and electrochemical methods and has been termed pyroprocessing. The process has been operated at full scale with simulated spent fuel using nonradioactive fission product elements. A comprehensive demonstration of the pyroprocessing of irradiated IFR fuel will begin later this year. Pyroprocessing involves the anodic dissolution of all the constituent elements of the IFR spent fuel and controlled electrotransport (electrorefining) to separate the actinide elements from the fission products present in the spent fuel. The process be applied to the processing of spent light water reactor (LWR) fuel as well, requiring only the addition of a reduction step to convert the LWR fuel as well, requiring only the addition of a reduction step to convert the LWR oxide fuel to metallic form and a separation step to separate uranium from the transuranic (TRU) elements. The TRU elements are then recovered by electroefining in the same manner as the actinides from the IFR high-level wastes arising from pyroprocessing are virtually free of actinides, and the volume of the wastes is minimized by the intrinsic characteristics of the processing of the processing method.

Laidler, J.J. (Argonne National Lab., IL (United States))

1993-01-01T23:59:59.000Z

168

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

Office of Environmental Management (EM)

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Full Document and Summary Versions...

169

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network [OSTI]

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency left intentionally blank.] #12;Prepared for the U.S. Department of Energy PNNL-SA-69994 under Contract DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL

170

Development of Vitrification Process and Glass Formulation for Nuclear Waste Conditioning  

SciTech Connect (OSTI)

The vitrification of high-level waste is the internationally recognized standard to minimize the impact to the environment resulting from waste disposal as well as to minimize the volume of conditioned waste to be disposed of. COGEMA has been vitrifying high-level waste industrially for over 20 years and is currently operating three commercial vitrification facilities based on a hot metal crucible technology, with outstanding records of safety, reliability and product quality. To further increase the performance of vitrification facilities, CEA and COGEMA have been developing the cold crucible melter technology since the beginning of the 1980s. This type of melter is characterized by a virtually unlimited equipment service life and a great flexibility in dealing with various types of waste and allowing development of high temperature matrices. In complement of and in parallel with the vitrification process, a glass formulation methodology has been developed by the CEA in order to tailor matrices for the wastes to be conditioned while providing the best adaptation to the processing technology. The development of a glass formulation is a trade-off between material properties and qualities, technical feasibility, and disposal safety criteria. It involves non-radioactive and radioactive laboratories in order to achieve a comprehensive matrix qualification. Several glasses and glass ceramics have thus been studied by the CEA to be compliant with industrial needs and waste characteristics: glasses or other matrices for a large spectrum of fission products, or for high contents of specifics elements such as sodium, phosphate, iron, molybdenum, or actinides. New glasses or glass-ceramics designed to minimize the final wasteform volume for solutions produced during the reprocessing of high burnup fuels or to treat legacy wastes are now under development and take benefit from the latest CEA hot-laboratories and technology development. The paper presents the CEA state-of-the-art in developing matrices or glasses and provides several examples.

Petitjean, V.; Fillet, C.; Boen, R.; Veyer, C.; Flament, T.

2002-02-26T23:59:59.000Z

171

Europe's danger  

Science Journals Connector (OSTI)

... ), these included the establishment of a committee to conduct a feasibility study on a synchroton radiation facility, progress of an ad hoc group on taxonomy in the fields of ...

Chris Sherwell

1977-11-10T23:59:59.000Z

172

Underlying Dangers  

Science Journals Connector (OSTI)

......comprising the use of tokens, certificates and biometrics for user end-point authentication and symmetric and asymmetric encryption...use of the deficiencies of yesterday's idyllic intentions. Humankind has now found itself in a situation where we are in an electronic......

David Bird

2013-01-01T23:59:59.000Z

173

An assessment of the flammability and explosion potential of transuranic waste  

SciTech Connect (OSTI)

The explosion potential of transuranic (TRU) waste, destined for the Waste Isolation Pilot (WIPP), was recently examined in EEG-45. That investigation focused on the volatile organic compounds (VOCs) in the waste, particularly acetone, and concluded that an explosion due to the VOCs was unlikely. Recent evidence raises serious concerns about drums containing mixed radioactive hazardous waste bound for the WIPP. Static electricity generated by the plastic bags represents a potential ignition source for other fuels, such as methane gas or hydrogen gas, during transportation and during the test phase. The potential danger of explosion due to hydrogen gas or methane gas generation has not yet been resolved. This report investigates that potential hazard and examines documented ignitions, fires, explosions and incidents of overpressurization of containers at generating and storage sites planning to send transuranic waste to the WIPP for disposal. 68 refs., 6 figs.

Silva, M.

1991-06-01T23:59:59.000Z

174

Waste Processing | Department of Energy  

Office of Environmental Management (EM)

Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Centers Cask Processing Enclosure. Workers process and repackage waste at...

175

Waste Hoist  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

176

Universit d'Angers L3 P " rie d9exeries nIF sxiqesyxF 2008-2009  

E-Print Network [OSTI]

Université d'Angers L3 P " érie d9exeries n¦IF sxiqesyxF 2008-2009 ixerie IF i) Soient X et Y deux

Menichi, Luc

177

Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina  

Broader source: Energy.gov (indexed) [DOE]

Impact Impact \ DoE/Els-o120 Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina Volume 3 Q ~+ ~ FNT O&@+@ &v a w ~ k ~ ;%." $ +6 & ~+e $TiTES Of December 1987 United States Department of Energy TABLE OF CONTENTS ~pendix G ASSESSMENT OF ALTERNATIVE STRATEGIES FOR STORAGE FACILITIES . . . . . . . . . . . G.1 No-Action Strategy . . . . . . . . G.1.l Sununarv and Objectives . . NEW DISPOSAL/ . . . . . . . . . . . . . . . G.1.2 Groundwater and Surface Water Effects G.1.3 Nonradioactive Atmospheric Releases . G.1.4 Ecological Effects . . . . . . . . . G.1.5 Radiological Releases . . . . . . . . G.1.6 Archaeological and Historic Resources G.1.7 SOciOecOnOmics . . . . . . . . . . . G.1.8 Dedication of Site . . . . . . . . . G.1.9 Institutional Impacts . . . . . . . . G.l.10 Noise . . . . . . . . . . . . . . . . G.2 Dedication Strategy . . . . . . . . . . . . . G.2.1 G.2.2 G.2.3 G.2.4 G.2.5 G.2.6

178

Vitrification of Simulated Fernald K-65 Silo Waste at Low Temperature  

SciTech Connect (OSTI)

Vitrification is the technology that has been chosen to solidify approximately 18,000 tons of geologic mill tailings at the Fernald Environmental Management Project (FEMP) in Fernald, Ohio. The geologic mill tailings are residues from the processing of pitchlende ore during 1949-1958. These waste residues are contained in silos in Operable Unit 4 (OU4) at the FEMP facility. Operable Unit 4 is one of five operable units at the FEMP. Operable Unit 4 is one of five operable units at the FEMP. Operating Unit 4 consists of four concrete storage silos and their contents. Silos 1 and 2 contain K-65 mill tailing residues and a bentonite cap, Silo 3 contains non-radioactive metal oxides, and Silo 4 is empty.

Jantzen, C.M.

1999-03-15T23:59:59.000Z

179

Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required.

Not Available

1993-06-01T23:59:59.000Z

180

Emission of nanoparticles during combustion of waste biomass in fireplace  

Science Journals Connector (OSTI)

Contamination of air by solid particles is serious problem for human health and also environment. Small particles in nano-sizes are more dangerous than same weight of larger size. Negative effect namely of the solid particles depends on (i) number (ii) specific surface area (iii) respirability and (iv) bonding of others substances (e.g. PAHs As Cd Zn Cu etc.) which are higher for smaller (nano-sizes) particles compared to larger one. For this reason mentioned above this contribution deals with measuring of amount and distribution of nanoparticles produced form combustion of waste city biomass in small combustion unit with impactor DLPI.

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Hanford Low-Activity Waste Processing: Demonstration of the Off-Gas Recycle Flowsheet - 13443  

SciTech Connect (OSTI)

Vitrification of Hanford Low-Activity Waste (LAW) is nominally the thermal conversion and incorporation of sodium salts and radionuclides into borosilicate glass. One key radionuclide present in LAW is technetium-99. Technetium-99 is a low energy, long-lived beta emitting radionuclide present in the waste feed in concentrations on the order of 1-10 ppm. The long half-life combined with a high solubility in groundwater results in technetium-99 having considerable impact on performance modeling (as potential release to the environment) of both the waste glass and associated secondary waste products. The current Hanford Tank Waste Treatment and Immobilization Plant (WTP) process flowsheet calls for the recycle of vitrification process off-gas condensates to maximize the portion of technetium ultimately immobilized in the waste glass. This is required as technetium acts as a semi-volatile specie, i.e. considerable loss of the radionuclide to the process off-gas stream can occur during the vitrification process. To test the process flowsheet assumptions, a prototypic off-gas system with recycle capability was added to a laboratory melter (on the order of 1/200 scale) and testing performed. Key test goals included determination of the process mass balance for technetium, a non-radioactive surrogate (rhenium), and other soluble species (sulfate, halides, etc.) which are concentrated by recycling off-gas condensates. The studies performed are the initial demonstrations of process recycle for this type of liquid-fed melter system. This paper describes the process recycle system, the waste feeds processed, and experimental results. Comparisons between data gathered using process recycle and previous single pass melter testing as well as mathematical modeling simulations are also provided. (authors)

Ramsey, William G.; Esparza, Brian P. [Washington River Protection Solutions, LLC, Richland, WA 99532 (United States)] [Washington River Protection Solutions, LLC, Richland, WA 99532 (United States)

2013-07-01T23:59:59.000Z

182

1994 Report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect (OSTI)

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) Milestone M-26-00 (Ecology et al. 1992). The text of this milestone is below. LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the US Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration at other action plan milestones and will not become effective until approved by the US Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: waste characterization plan; storage report; treatment report; treatment plan; waste minimization plan; a schedule depicting the events necessary to achieve full compliance with LDR requirements; a process for establishing interim milestones. The original plan was published in October 1990. This is the fourth of a series of annual updates required by Tri-Party Agreement Milestone M-26-01. A Tri-Party Agreement change request approved in March 1992 changed the annual due date from October to April and consolidated this report with a similar one prepared under Milestone M-25-00. The reporting period for this report is from April 1, 1993, to March 31, 1994.

Black, D.G.

1994-04-01T23:59:59.000Z

183

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

184

DOWNSTREAM IMPACTS OF SLUDGE MASS REDUCTION VIA ALUMINUM DISSOLUTION ON DWPF PROCESSING OF SAVANNAH RIVER SITE HIGH LEVEL WASTE - 9382  

SciTech Connect (OSTI)

The SRS sludge that was to become a major fraction of Sludge Batch 5 (SB5) for the Defense Waste Processing Facility (DWPF) contained a large fraction of H-Modified PUREX (HM) sludge, containing a large fraction of aluminum compounds that could adversely impact the processing and increase the vitrified waste volume. It is beneficial to reduce the non-radioactive fraction of the sludge to minimize the number of glass waste canisters that must be sent to a Federal Repository. Removal of aluminum compounds, such as boehmite and gibbsite, from sludge can be performed with the addition of NaOH solution and heating the sludge for several days. Preparation of SB5 involved adding sodium hydroxide directly to the waste tank and heating the contents to a moderate temperature through slurry pump operation to remove a fraction of this aluminum. The Savannah River National Laboratory (SRNL) was tasked with demonstrating this process on actual tank waste sludge in our Shielded Cells Facility. This paper evaluates some of the impacts of aluminum dissolution on sludge washing and DWPF processing by comparing sludge processing with and without aluminum dissolution. It was necessary to demonstrate these steps to ensure that the aluminum removal process would not adversely impact the chemical and physical properties of the sludge which could result in slower processing or process upsets in the DWPF.

Pareizs, J; Cj Bannochie, C; Michael Hay, M; Daniel McCabe, D

2009-01-14T23:59:59.000Z

185

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

186

Transuranic Waste Requirements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

1999-07-09T23:59:59.000Z

187

Waste?to?Energy  

Broader source: Energy.gov [DOE]

Waste?to?Energy Roadmapping Workshop Waste?to?Energy Presentation by Jonathan Male, Director of the Bioenery Technolgies Office, Department of Energy

188

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

The term nuclear waste...embraces all residues from the use of radioactive materials, including uses in medicine and industry. The most highly radioactive of these are the spent fuel or reprocessed wastes from co...

2005-01-01T23:59:59.000Z

189

WasteTraining Booklet Waste & Recycling Impacts  

E-Print Network [OSTI]

WasteTraining Booklet #12;Waste & Recycling Impacts Environment: The majority of our municipal jobs while recycling 10,000 tons of waste creates 36 jobs. Environment: Recycling conserves resources. It takes 95% less energy to make aluminum from recycled aluminum than from virgin materials, 60% less

Saldin, Dilano

190

Alternatives for the disposal of NORM (naturally occurring radioactive materials) wastes in Texas  

SciTech Connect (OSTI)

Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios.

Nielson, K.K.; Rogers, V.C. (Rogers Associates Engineering Corporation, Salt Lake City, UT (USA)); Pollard, C.G. (Texas Low-Level Radioactive Waste Disposal Authority, Austin (USA))

1989-11-01T23:59:59.000Z

191

E-waste education strategies: teaching how to reduce, reuse and recycle for sustainable development  

Science Journals Connector (OSTI)

The constantly changing world of technology is the world's largest and fastest growing manufacturing industry. The vast growth and rapid product obsolescence has brought about the serious problem of e-waste, which is now the fastest growing form of waste in the industrialised world. E-waste encompasses a broad and growing category of electronic devices ranging from large household appliances such as refrigerators, microwave ovens and air conditioners to consumer electronics such as cellular phones, televisions, personal stereos and computers. Electronic equipment contains a variety of toxic ingredients, including hazardous heavy metals that pollute the environment and are very dangerous to human health. This paper discusses some of the principles that are being employed to alleviate the environmental impact of e-waste such as extended producer responsibility, design for environment (DfE), consumer driven solutions. This article also discusses educational strategies that can be employed to educate global audiences.

Phillip Olla; Joseph Toth

2010-01-01T23:59:59.000Z

192

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

193

Materials performance in a high-level radioactive waste vitrification system  

SciTech Connect (OSTI)

The Defense Waste Processing Facility (DWPF) is a Department of Energy Facility designed to vitrify highly radioactive waste. An extensive materials evaluation program has been completed on key components in the DWPF after twelve months of operation using nonradioactive simulated wastes. Results of the visual inspections of the feed preparation system indicate that the system components, which were fabricated from Hastelloy C-276, should achieve their design lives. Significant erosion was observed on agitator blades that process glass frit slurries; however, design modifications should mitigate the erosion. Visual inspections of the DWPF melter top head and off gas components, which were fabricated from Inconel 690, indicated that varying degrees of degradation occurred. Most of the components will perform satisfactorily for their two year design life. The components that suffered significant attack were the borescopes, primary film cooler brush, and feed tubes. Changes in the operation of the film cooler brush and design modifications to the feed tubes and borescopes is expected to extend their service lives to two years. A program to investigate new high temperature engineered materials and alloys with improved oxidation and high temperature corrosion resistance will be initiated.

Imrich, K.J.; Chandler, G.T.

1996-06-17T23:59:59.000Z

194

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

1999-07-09T23:59:59.000Z

195

Helium solubility in SON68 nuclear waste glass  

SciTech Connect (OSTI)

Helium behavior in a sodium borosilicate glass (SON68) dedicated to the immobilization of high-level nuclear waste is examined. Two experimental approaches on nonradioactive glass specimens are implemented: pressurized helium infusion experiments and {sup 3}He ion implantation experiments. The temperature variation of helium solubility in SON68 glass was determined and analyzed with the harmonic oscillator model to determine values of the energy of interaction E(0) at the host sites (about -4000 J/mol), the vibration frequency (about 1.7 x 10{sup 11} s{sup -1}), and the density of solubility sites (2.2 x 10{sup 21} sites cm{sup -3}). The implantation experiments show that a non diffusive transport phenomenon (i.e., athermal diffusion) is involved in the material when the helium concentration exceeds 2.3 x 10{sup 21} He cm{sup -3}, and thus probably as soon as it exceeds the density of solubility sites accessible to helium in the glass. We propose that this transport mechanism could be associated with the relaxation of the stress gradient induced by the implanted helium profile, which is favored by the glass damage. Microstructural characterization by TEM and ESEM of glass specimens implanted with high helium concentrations showed a homogeneous microstructure free of bubbles, pores, or cracking at a scale of 10 nm. (authors)

Fares, Toby; Peuget, Sylvain; Bouty, Olivier; Broudic, Veronique; Maugeri, Emilio; Bes, Rene; Jegou, Christophe [CEA, DEN, DTCD SECM LMPA, F-30207 Marcoule, Bagnols Sur Cez, (France); Chamssedine, Fadel; Sauvage, Thierry [CNRS, CEMHTI, F-245071 Orleans, (France); Deschanels, Xavier [LNAR, Marcoule Inst Separat Chem, F-30207 Bagnols Sur Ceze, (France)

2012-12-15T23:59:59.000Z

196

Remaining Sites Verification Package for the 1607-B1 Septic System, Waste Site Reclassification Form 2007-015  

SciTech Connect (OSTI)

The 1607-B1 Septic System includes a septic tank, drain field, and associated connecting pipelines and influent sanitary sewer lines. This septic system serviced the former 1701-B Badgehouse, 1720-B Patrol Building/Change Room, and the 1709-B Fire Headquarters. The 1607-B1 waste site received unknown amounts of nonhazardous, nonradioactive sanitary sewage from these facilities during its operational history from 1944 to approximately 1970. In accordance with this evaluation, the confirmatory sampling results support a reclassification of this site to No Action. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of confirmatory sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

L. M. Dittmer

2007-08-30T23:59:59.000Z

197

Dangerous climate change and the importance of adaptation for the Arctic's Inuit  

Science Journals Connector (OSTI)

The Arctic's climate is changing rapidly, to the extent that 'dangerous' climate change as defined by the United Nations Framework on Climate Change might already be occurring. These changes are having implications for the Arctic's Inuit population and are being exacerbated by the dependence of Inuit on biophysical resources for livelihoods and the low socio-economic–health status of many northern communities. Given the nature of current climate change and projections of a rapidly warming Arctic, climate policy assumes a particular importance for Inuit regions. This paper argues that efforts to stabilize and reduce greenhouse gas emissions are urgent if we are to avoid runaway climate change in the Arctic, but unlikely to prevent changes which will be dangerous for Inuit. In this context, a new policy discourse on climate change is required for Arctic regions—one that focuses on adaptation. The paper demonstrates that states with Inuit populations and the international community in general has obligations to assist Inuit to adapt to climate change through international human rights and climate change treaties. However, the adaptation deficit, in terms of what we know and what we need to know to facilitate successful adaptation, is particularly large in an Arctic context and limiting the ability to develop response options. Moreover, adaptation as an option of response to climate change is still marginal in policy negotiations and Inuit political actors have been slow to argue the need for adaptation assistance. A new focus on adaptation in both policy negotiations and scientific research is needed to enhance Inuit resilience and reduce vulnerability in a rapidly changing climate.

James D Ford

2009-01-01T23:59:59.000Z

198

Is alcohol more dangerous than heroin? The physical, social and financial costs of alcohol  

Science Journals Connector (OSTI)

A recent paper claimed in its classification of harmful substances, that alcohol is more dangerous than heroin. This paper aims to weigh up some of the evidence in the literature on the physical, social and financial effects of alcohol and the associated disease burden. We will also explore alcohol within the context of emergency department (ED) presentations. Reasons for ED attendance can be overtly and directly alcohol related such as alcohol intoxication, assaults, injuries and falls and indirectly such as child neglect, psychological problems and chronic diseases. Alcohol is often viewed as an isolated incident or factor for ED presentations but there are data that refute this perception. In ED, the priority is to treat the patient and their primary complaint, however it may be appropriate to screen for alcohol use, give advice and potentially offer an intervention to the patient. With the recent UK and Australian guidelines on reducing health risks from drinking alcohol, the ED has the ability to play an active role in reducing the harmful effects of alcohol through screening, advising and undertaking intervention as appropriate. However this cannot be achieved in isolation but within the broader political and health policy framework. There is now a growing body of literature supporting the need to make alcohol less affordable, less easy to buy and reducing alcohol advertising. Although alcohol is a legal substance, this paper concludes that examining the wider effects in physical, social and financial terms, alcohol is more dangerous than heroin. It has become an endemic problem in society affecting the individual and the whole community.

Geraldine A. Lee; Marcus Forsythe

2011-01-01T23:59:59.000Z

199

Waste-to-Energy: Waste Management and Energy Production Opportunities...  

Office of Environmental Management (EM)

Waste-to-Energy: Waste Management and Energy Production Opportunities Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S....

200

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

Broader source: Energy.gov (indexed) [DOE]

and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes Air Products and Chemicals, Inc. - Allentown, PA A microbial reverse electrodialysis...

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

Broader source: Energy.gov (indexed) [DOE]

(ex: organic Rankine cycle) High installed KW capital Low temperature waste heat (<100C) is not practicable Further efficiency loss in electrolytic conversion to...

202

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

203

Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term  

SciTech Connect (OSTI)

Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer`s equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs.

Hobart, D.E. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Glenn T. Seaborg Inst. for Transactinium Science, Livermore, CA (United States); Bruton, C.J. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Lawrence Livermore National Lab., CA (United States). Earth Sciences Dept.; Millero, F.J. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Univ. of Miami, FL (United States). Rosenstiel School of Marine and Atmospheric Science; Chou, I.M. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Geological Survey, Reston, VA (United States); Trauth, K.M.; Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States)

1996-05-01T23:59:59.000Z

204

DEMONSTRATION OF THE NEXT-GENERATION CAUSTIC-SIDE SOLVENT EXTRACTION SOLVENT WITH 2-CM CENTRIGUGAL CONTRACTORS USING TANK 49H WASTE AND WASTE SIMULANT  

SciTech Connect (OSTI)

Researchers successfully demonstrated the chemistry and process equipment of the Caustic-Side Solvent Extraction (CSSX) flowsheet using MaxCalix for the decontamination of high level waste (HLW). The demonstration was completed using a 12-stage, 2-cm centrifugal contactor apparatus at the Savannah River National Laboratory (SRNL). This represents the first CSSX process demonstration of the MaxCalix solvent system with Savannah River Site (SRS) HLW. Two tests lasting 24 and 27 hours processed non-radioactive simulated Tank 49H waste and actual Tank 49H HLW, respectively. A solvent extraction system for removal of cesium from alkaline solutions was developed utilizing a novel solvent invented at the Oak Ridge National Laboratory (ORNL). This solvent consists of a calix[4]arene-crown-6 extractant dissolved in an inert hydrocarbon matrix. A modifier is added to the solvent to enhance the extraction power of the calixarene and to prevent the formation of a third phase. An additional additive is used to improve stripping performance and to mitigate the effects of any surfactants present in the feed stream. The process that deploys this solvent system is known as Caustic Side Solvent Extraction (CSSX). The solvent system has been deployed at the Savannah River Site (SRS) in the Modular CSSX Unit (MCU) since 2008.

Pierce, R.; Peters, T.; Crowder, M.; Pak, D.; Fink, S.; Blessing, R.; Washington, A.; Caldwell, T.

2011-11-29T23:59:59.000Z

205

Development of Technology for Immobilization of Waste Salt from Electrorefining Spent Nuclear Fuel in Zeolite-A for Eventual Disposition in a Ceramic Waste Form  

SciTech Connect (OSTI)

The results of process development for the blending of waste salt from the electrorefining of spent fuel with zeolite-A are presented. This blending is a key step in the ceramic waste process being used for treatment of EBR-II spent fuel and is accomplished using a high-temperature v-blender. A labscale system was used with non-radioactive surrogate salts to determine optimal particle size distributions and time at temperature. An engineering-scale system was then installed in the Hot Fuel Examination Facility hot cell and used to demonstrate blending of actual electrorefiner salt with zeolite. In those tests, it was shown that the results are still favorable with actinide-loaded salt and that batch size of this v-blender could be increased to a level consistent with efficient production operations for EBR-II spent fuel treatment. One technical challenge that remains for this technology is to mitigate the problem of material retention in the v-blender due to formation of caked patches of salt/zeolite on the inner v-blender walls.

Michael F. Simpson; Prateek Sachdev

2008-04-01T23:59:59.000Z

206

Decontamination and inspection plan for Phase 3 closure of the 300 area waste acid treatment system  

SciTech Connect (OSTI)

This decontamination and inspection plan (DIP) describes decontamination and verification activities in support of Phase 3 closure of the 300 Area Waste Acid Treatment System (WATS). Phase 3 is the third phase of three WATS closure phases. Phase 3 attains clean closure conditions for WATS portions of the 334 and 311 Tank Farms (TF) and the 333 and 303-F Buildings. This DIP also describes designation and management of waste and debris generated during Phase 3 closure activities. Information regarding Phase 1 and Phase 2 for decontamination and verification activities closure can be found in WHC-SD-ENV-AP-001 and HNF-1784, respectively. This DIP is provided as a supplement to the closure plan (DOE/RL-90-11). This DIP provides the documentation for Ecology concurrence with Phase 3 closure methods and activities. This DIP is intended to provide greater detail than is contained in the closure plan to satisfy Ecology Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 requirement that closure documents describe the methods for removing, transporting, storing, and disposing of all dangerous waste at the unit. The decontamination and verification activities described in this DIP are based on the closure plan and on agreements reached between Ecology and the U.S. Department of Energy, Richland Operations Office (DOE-RL) during Phase 3 closure activity workshops and/or project manager meetings (PMMs).

LUKE, S.N.

1999-02-01T23:59:59.000Z

207

Microsoft Word - EA_Draft 051110_final_acl.docx  

Broader source: Energy.gov (indexed) [DOE]

707D 707D May 2010 DOE/EA-1707D Draft Environmental Assessment iii May 2010 Summary 1 Introduction. This Environmental Assessment (EA) provides information and analyses of proposed 2 U.S. Department of Energy (DOE) activities associated with closure of the DOE Hanford Site's 3 Nonradioactive Dangerous Waste Landfill (NRDWL) and the Solid Waste Landfill (SWL). 4 Purpose and Need. The DOE needs to close the non-operating NRDWL. This facility has not received 5 waste since 1988 (i.e., a non-operating facility), and would be closed according to Resource Conservation 6 and Recovery Act of 1976 (RCRA) requirements as implemented through the Hazardous Waste 7 Management Act and Washington State Dangerous Waste Regulations (WAC 173-303). To achieve 8

208

Why young birds forage at nutritionally poor and dangerous places: classical food-safety trade-offs  

E-Print Network [OSTI]

in the context of energy state. Animals in low energy states tend to accept the highest danger levels in return for higher energy gains. However, successful foraging requires animals to be able to find and handle food this study was carried out, Red Knot feed at low tide, mostly on seagrass meadows. During high tide they have

Sandercock, Brett K.

209

Boiling Water at Hot Creek--The Dangerous and Dynamic Thermal Springs in California's Long Valley Caldera  

E-Print Network [OSTI]

Boiling Water at Hot Creek--The Dangerous and Dynamic Thermal Springs in California's Long Valley.S. Geological Survey USGS Fact Sheet 2007-3045 2007 T Hot Creek flows through the Long Valley Caldera Airport Fish hatchery CH-10B 44-16 Well Well Long Valley C aldera Area of Map Californ i a The thermal

Torgersen, Christian

210

On the dangers of C. I. S. specialists with nuclear weapons experience relocating to Third World countries: A Russian view  

SciTech Connect (OSTI)

This newsletter presents information on the effectiveness of rules and regulations; on the role of a qualified consultant in the possible design of a nuclear weapon for a Third World country; and on the possible dangers (and their elimination) of relocating nuclear technologists.

Hogsett, V.; Canavan, B. (eds.)

1993-01-01T23:59:59.000Z

211

Assessing "Dangerous Climate Change": Required Reduction of Carbon Emissions to Protect Young People, Future Generations and Nature  

E-Print Network [OSTI]

Assessing "Dangerous Climate Change": Required Reduction of Carbon Emissions to Protect Young high and would subject young people, future generations and nature to irreparable harm. Carbon dioxide (CO2) emissions from fossil fuel use must be reduced rapidly to avoid irreversible consequences

Hansen, James E.

212

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network [OSTI]

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

213

The Climate + Energy Project is excited to announce an exclusive screening of the docu-series about climate change, YEARS OF LIVING DANGEROUSLY.  

E-Print Network [OSTI]

-series about climate change, YEARS OF LIVING DANGEROUSLY. The 9-part series premiered on April 13, 2014. CEP on Climate Change (IPCC) Reports. Tuesday, November 11th , Lawrence Years of Living Dangerously events: FilmThe Climate + Energy Project is excited to announce an exclusive screening of the SHOWTIME® docu

214

THIS FORM MUST BE COMPLETED FOR ANY INJURY,WORK RELATED ILL HEALTH, DANGEROUS OCCURRENCE AND NEAR MISS IN RESPECT OF STAFF, STUDENTS, CONTRACTORS AND VISITORS  

E-Print Network [OSTI]

THIS FORM MUST BE COMPLETED FOR ANY INJURY,WORK RELATED ILL HEALTH, DANGEROUS OCCURRENCE AND NEAR or manager may do so on their behalf. Dangerous Work related Accident Occurrence ill health Near Miss Full departmental manager for advice or contact the Health and Safety Unit on extension number 3317. · A copy

215

Article in Kathimerini, August 9, 2006: Rubbish dumps spell danger The public health hazard posed by the approximately 2,000 rubbish dumps currently  

E-Print Network [OSTI]

Article in Kathimerini, August 9, 2006: Rubbish dumps spell danger The public health hazard posed recently burned trash for more than a week. Researchers at the Democritus University found dangerous levels in which to play out political and economic interests. By sacrificing the good health of their residents

Columbia University

216

Recycled Water Reuse Permit Renewal Application for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond  

SciTech Connect (OSTI)

ABSTRACT This renewal application for the Industrial Wastewater Reuse Permit (IWRP) WRU-I-0160-01 at Idaho National Laboratory (INL), Materials and Fuels Complex (MFC) Industrial Waste Ditch (IWD) and Industrial Waste Pond (IWP) is being submitted to the State of Idaho, Department of Environmental Quality (DEQ). This application has been prepared in compliance with the requirements in IDAPA 58.01.17, Recycled Water Rules. Information in this application is consistent with the IDAPA 58.01.17 rules, pre-application meeting, and the Guidance for Reclamation and Reuse of Municipal and Industrial Wastewater (September 2007). This application is being submitted using much of the same information contained in the initial permit application, submitted in 2007, and modification, in 2012. There have been no significant changes to the information and operations covered in the existing IWRP. Summary of the monitoring results and operation activity that has occurred since the issuance of the WRP has been included. MFC has operated the IWP and IWD as regulated wastewater land treatment facilities in compliance with the IDAPA 58.01.17 regulations and the IWRP. Industrial wastewater, consisting primarily of continuous discharges of nonhazardous, nonradioactive, routinely discharged noncontact cooling water and steam condensate, periodic discharges of industrial wastewater from the MFC facility process holdup tanks, and precipitation runoff, are discharged to the IWP and IWD system from various MFC facilities. Wastewater goes to the IWP and IWD with a permitted annual flow of up to 17 million gallons/year. All requirements of the IWRP are being met. The Operations and Maintenance Manual for the Industrial Wastewater System will be updated to include any new requirements.

No Name

2014-10-01T23:59:59.000Z

217

Hazardous Waste Management (Oklahoma)  

Broader source: Energy.gov [DOE]

This article states regulations for the disposal of hazardous waste. It also provides information about permit requirements for the transport, treatment and storage of such waste. It also mentions...

218

Nuclear waste solids  

Science Journals Connector (OSTI)

Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since releas...

L. L. Hench; D. E. Clark; A. B. Harker

1986-05-01T23:59:59.000Z

219

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

220

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network [OSTI]

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Radionuclide Retention Mechanisms in Secondary Waste-Form Testing: Phase II  

SciTech Connect (OSTI)

This report describes the results from laboratory tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate candidate stabilization technologies that have the potential to successfully treat liquid secondary waste stream effluents produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). WRPS is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF, a multi-waste, treatment-and-storage unit that has been permitted under the Resource Conservation and Recovery Act (RCRA), can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid waste generated during operation of the WTP. The STU will provide the additional capacity needed for ETF to process the increased volume of secondary waste expected to be produced by WTP. This report on radionuclide retention mechanisms describes the testing and characterization results that improve understanding of radionuclide retention mechanisms, especially for pertechnetate, {sup 99}TcO{sub 4}{sup -} in four different waste forms: Cast Stone, DuraLith alkali aluminosilicate geopolymer, encapsulated fluidized bed steam reforming (FBSR) product, and Ceramicrete phosphate bonded ceramic. These data and results will be used to fill existing data gaps on the candidate technologies to support a decision-making process that will identify a subset of the candidate waste forms that are most promising and should undergo further performance testing.

Um, Wooyong; Valenta, Michelle M.; Chung, Chul-Woo; Yang, Jungseok; Engelhard, Mark H.; Serne, R. Jeffrey; Parker, Kent E.; Wang, Guohui; Cantrell, Kirk J.; Westsik, Joseph H.

2011-09-26T23:59:59.000Z

222

1993 report on Hanford Site land disposal restrictions for mixed wastes  

SciTech Connect (OSTI)

Since the early 1940s, the contractors at the Hanford Site have 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 (RMW). This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976{sup 2}(RCRA) and Atomic Energy Act{sup 3}. This report covers mixed waste only. Hazardous waste that is not contaminated with radionuclides is not addressed in this report. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order{sup 1} (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for RMW. This report is the third update of the plan first issued in 1990. The Tri-Party Agreement requires, and the baseline plan and annual update reports provide, the information that follows: Waste characterization information; storage data; treatment information; waste reduction information; schedule; and progress.

Black, D.

1993-04-01T23:59:59.000Z

223

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

224

Project management plan for low-level mixed waste and greater-than-category 3 waste per tri-party agreement M-91-10  

SciTech Connect (OSTI)

The objective of this project management plan is to define the tasks and deliverables that will support the treatment, storage, and disposal of remote-handled and large container contact-handled low-level mixed waste, and the storage of Greater-thaw category 3 waste. The plan is submitted to fulfill the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-91-10, The plan was developed in four steps: (1) the volumes of the applicable waste streams and the physical, dangerous, and radioactive characteristics were established using existing databases and forecasts; (2) required treatment was identified for each waste stream based on land disposal restriction treatment standards and waste characterization data; (3) alternatives for providing the required treatment were evaluated and the preferred options were selected; (4) an acquisition plan was developed to establish the technical, schedule, and cost baselines for providing the required treatment capabilities. The major waste streams are tabulated, along with the required treatment for disposal.

BOUNINI, L.

1999-05-20T23:59:59.000Z

225

Project management plan for low-level mixed wastes and greater-than category 3 waste per Tri-Party Agreement M-91-10  

SciTech Connect (OSTI)

The objective of this project management plan is to define the tasks and deliverables that will support the treatment, storage, and disposal of remote-handled and large container contact-handled low-level mixed waste, and the storage of Greater-Than-Category 3 waste. The plan is submitted to fulfill the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-91-10. The plan was developed in four steps: (1) the volumes of the applicable waste streams and the physical, dangerous, and radioactive characteristics were established using existing databases and forecasts; (2) required treatment was identified for each waste stream based on land disposal restriction treatment standards and waste characterization data; (3) alternatives for providing the required treatment were evaluated and the preferred options were selected; and (4) an acquisition plan was developed to establish the techuical, schedule, and cost baselines for providing the required treatment capabilities. The major waste streams are summarized in the table below, along with the required treatment for disposal.

BOUNINI, L.

1999-06-17T23:59:59.000Z

226

The exposure–damage approach in the quantification of occupational risk in workplaces involving dangerous substances  

Science Journals Connector (OSTI)

The work proposes a new approach for the quantification of occupational risk overcoming the limitations of the common qualitative methodologies widely used by industry and authorities. The proposed methodological approach has been developed at the Technical University of Crete and is based on the principles of quantitative risk assessment (QRA) for the control of major-accident hazards involving dangerous substances. It aims at establishing a systematic risk analysis tool for the quantitative assessment of occupational risk. The index of ‘individual occupational risk’ is introduced as a probability function of four variables, normalized over actual working time: the frequency of an active hazard, the probability of an employee being present at a work-place, the extent of distinct consequence zones and the employee vulnerability. The methodology has been applied to several industrial environments and has verified its potentiality to provide documented support on important decisions on occupational (health and safety) improving measures related to process safety conditions, job management, protective systems, consequence mitigation measures and personal protective measures.

G.A. Papadakis; A.A. Chalkidou

2008-01-01T23:59:59.000Z

227

Vitrification of surrogate mixed wastes in a graphite electrode arc melter  

SciTech Connect (OSTI)

Demonstration tests for vitrifying mixed wastes and contaminated soils have been conducted using a small (800 kVA), industrial-scale, three-phase AC, graphite electrode furnace located at the Albany Research Center of the United States Bureau of Mines (USBM). The feed mixtures were non-radioactive surrogates of various types of mixed (radioactive and hazardous), transuranic-contaminated wastes stored and buried at the Idaho National Engineering Laboratory (INEL). The feed mixtures were processed with added soil from the INEL. Objectives being evaluated include (1) equipment capability to achieve desired process conditions and vitrification products for different feed compositions, (2) slag and metals tapping capability, (3) partitioning of transuranic elements and toxic metals among the furnace products, (4) slag, fume, and metal products characteristics, and (5) performance of the feed, furnace and air pollution control systems. The tests were successfully completed in mid-April 1995. A very comprehensive process monitoring, sampling and analysis program was included in the test program. Sample analysis, data reduction, and results evaluation are currently underway. Initial results indicate that the furnace readily processed around 20,000 lb of widely ranging feed mixtures at feedrates of up to 1,100 lb/hr. Continuous feeding and slag tapping was achieved. Molten metal was also tapped twice during the test program. Offgas emissions were efficiently controlled as expected by a modified air pollution control system.

Soelberg, N.R.; Chambers, A.G.; Ball, L. [and others

1995-11-01T23:59:59.000Z

228

Process Testing Results and Scaling for the Hanford Waste Treatment and Immobilization Plant (WTP) Pretreatment Engineering Platform - 10173  

SciTech Connect (OSTI)

The U.S. Department of Energy-Office of River Protection’s Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being designed and built to pretreat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks at Richland, Washington. In support of this effort, engineering-scale tests at the Pretreatment Engineering Platform (PEP) have been completed to confirm the process design and provide improved projections of system capacity. The PEP is a 1/4.5-scale facility designed, constructed, and operated to test the integrated leaching and ultrafiltration processes being deployed at the WTP. The PEP replicates the WTP leaching processes with prototypic equipment and control strategies and non-prototypic ancillary equipment to support the core processing. The testing approach used a nonradioactive aqueous slurry simulant to demonstrate the unit operations of caustic and oxidative leaching, cross-flow ultrafiltration solids concentration, and solids washing. Parallel tests conducted at the laboratory scale with identical simulants provided results that allow scale-up factors to be developed between the laboratory and PEP performance. This paper presents the scale-up factors determined between the laboratory and engineering-scale results and presents arguments that extend these results to the full-scale process.

Kurath, Dean E.; Daniel, Richard C.; Baldwin, David L.; Rapko, Brian M.; Barnes, Steven M.; Gilbert, Robert A.; Mahoney, Lenna A.; Huckaby, James L.

2010-01-14T23:59:59.000Z

229

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents &...

230

Waste Isolation Pilot Plant Transportation Security | Department...  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security More Documents &...

231

Simulant Development for Hanford Double-Shell Tank Mixing and Waste Feed Delivery Testing  

SciTech Connect (OSTI)

The U.S. Department of Energy Office of River Projection manages the River Protection Project, which has the mission to retrieve and treat the Hanford tank waste for disposal and close the tank farms (Certa et al. 2011). Washington River Protection Solutions, LLC (WRPS) is responsible for a primary objective of this mission which is to retrieve and transfer tank waste to the Hanford Waste Treatment and Immobilization Plant (WTP). A mixing and sampling program with four separate demonstrations is currently being conducted to support this objective and also to support activities in a plan for addressing safety concerns identified by the Defense Nuclear Facilities Safety Board related to the ability of the WTP to mix, sample, and transfer fast settling particles. Previous studies have documented the objectives, criteria, and selection of non-radioactive simulants for these four demonstrations. The identified simulants include Newtonian suspending liquids with densities and viscosities that span the range expected in waste feed tanks. The identified simulants also include non-Newtonian slurries with Bingham yield stress values that span a range that is expected to bound the Bingham yield stress in the feed delivery tanks. The previous studies identified candidate materials for the Newtonian and non-Newtonian suspending fluids, but did not provide specific recipes for obtaining the target properties and information was not available to evaluate the compatibility of the fluids and particles or the potential for salt precipitation at lower temperatures. The purpose of this study is to prepare small batches of simulants in advance of the demonstrations to determine specific simulant recipes, to evaluate the compatibility of the liquids and particles, and to determine if the simulants are stable for the potential range of test temperatures. The objective of the testing, which is focused primarily on the Newtonian and non-Newtonian fluids, is to determine the composition of simulant materials that give the desired density and viscosity or rheological parameters.

Gauglitz, Phillip A.; Tran, Diana N.; Buchmiller, William C.

2012-09-24T23:59:59.000Z

232

Tank Waste and Waste Processing | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

233

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

electrolytic cell, designed to integrate waste heat recovery (i.e a microbial heat recovery cell or MHRC), can operate as a fuel cell and convert effluent streams into...

234

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect (OSTI)

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

235

Solid Waste Management Plan. Revision 4  

SciTech Connect (OSTI)

The waste types discussed in this Solid Waste Management Plan are Municipal Solid Waste, Hazardous Waste, Low-Level Mixed Waste, Low-Level Radioactive Waste, and Transuranic Waste. The plan describes for each type of solid waste, the existing waste management facilities, the issues, and the assumptions used to develop the current management plan.

NONE

1995-04-26T23:59:59.000Z

236

Waste Confidence Discussion | Department of Energy  

Office of Environmental Management (EM)

Waste Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion More Documents & Publications Status Update: Extended Storage...

237

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

238

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting...

239

Ferrocyanide tank waste stability  

SciTech Connect (OSTI)

Ferrocyanide wastes were generated at the Hanford Site during the mid to late 1950s as a result of efforts to create more tank space for the storage of high-level nuclear waste. The ferrocyanide process was developed to remove [sup 137]CS from existing waste and newly generated waste that resulted from the recovery of valuable uranium in Hanford Site waste tanks. During the course of research associated with the ferrocyanide process, it was recognized that ferrocyanide materials, when mixed with sodium nitrate and/or sodium nitrite, were capable of violent exothermic reaction. This chemical reactivity became an issue in the 1980s, when safety issues associated with the storage of ferrocyanide wastes in Hanford Site tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety issues associated with these wastes, as well as current research and waste management programs. Testing to provide information on the nature of possible tank reactions is ongoing. This document supplements the information presented in Summary of Single-Shell Tank Waste Stability, WHC-EP-0347, March 1991 (Borsheim and Kirch 1991), which evaluated several issues. This supplement only considers information particular to ferrocyanide wastes.

Fowler, K.D.

1993-01-01T23:59:59.000Z

240

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

242

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network [OSTI]

Energy from Waste UK Joint Statement on Energy from Waste Read more overleaf Introduction Energy from waste provides us with an opportunity for a waste solution and a local source of energy rolled,itcan onlyaddressaportionofthewastestream andisnotsufficientonitsown. Energy obtained from the combustion of residual waste (Energy from

243

Stabilization of compactible waste  

SciTech Connect (OSTI)

This report summarizes the results of series of experiments performed to determine the feasibility of stabilizing compacted or compactible waste with polymers. The need for this work arose from problems encountered at disposal sites attributed to the instability of this waste in disposal. These studies are part of an experimental program conducted at Brookhaven National Laboratory (BNL) investigating methods for the improved solidification/stabilization of DOE low-level wastes. The approach taken in this study was to perform a series of survey type experiments using various polymerization systems to find the most economical and practical method for further in-depth studies. Compactible dry bulk waste was stabilized with two different monomer systems: styrene-trimethylolpropane trimethacrylate (TMPTMA) and polyester-styrene, in laboratory-scale experiments. Stabilization was accomplished by wetting or soaking compactible waste (before or after compaction) with monomers, which were subsequently polymerized. Three stabilization methods are described. One involves the in-situ treatment of compacted waste with monomers in which a vacuum technique is used to introduce the binder into the waste. The second method involves the alternate placement and compaction of waste and binder into a disposal container. In the third method, the waste is treated before compaction by wetting the waste with the binder using a spraying technique. A series of samples stabilized at various binder-to-waste ratios were evaluated through water immersion and compression testing. Full-scale studies were conducted by stabilizing two 55-gallon drums of real compacted waste. The results of this preliminary study indicate that the integrity of compacted waste forms can be readily improved to ensure their long-term durability in disposal environments. 9 refs., 10 figs., 2 tabs.

Franz, E.M.; Heiser, J.H. III; Colombo, P.

1990-09-01T23:59:59.000Z

244

Waste Inspection Tomography (WIT)  

SciTech Connect (OSTI)

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons.

Bernardi, R.T.

1995-12-01T23:59:59.000Z

245

State Environmental Policy Act (SEPA) Environmental Checklist Form 216-B-3 Expansion Ponds Closure Plan. Revision 1  

SciTech Connect (OSTI)

The 216-B-3 Expansion Ponds Closure Plan (Revision 1) consists of a Part A Dangerous Waste Permit Application and a Resource Conservation and Recovery Act Closure Plan. An explanation of the Part A submitted with this document is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. The 216-B-3 Pond System consists of a series of four earthen, unlined, interconnected ponds and the 216-B-3-3 Ditch that receive waste water from various 200 East Area operating facilities. These four ponds, collectively. Waste water (primarily cooling water, steam condensate, and sanitary water) from various 200 East Area facilities is discharged to the 216-B-3-3 Ditch. Water discharged to the 216-8-3-3 Ditch flows directly into the 216-B-3 Pond. In the past, waste water discharges to B Pond and the 216-B-3-3 Ditch contained mixed waste (radioactive waste and dangerous waste). The radioactive portion of mixed waste has been interpreted by the US Department of Energy (DOE) to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous portion of mixed waste is regulated under RCRA. Mixed waste also may be considered a hazardous substance under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) when considering remediation of waste sites.

Not Available

1993-12-01T23:59:59.000Z

246

Etre rom en Bulgarie : les dangers d'une essentialisation de l'altrit Nadge Ragaru1  

E-Print Network [OSTI]

1 Etre rom en Bulgarie : les dangers d'une essentialisation de l'altérité Nadège Ragaru1 Dans les imaginaires sociaux, les Roms relèvent tour à tour d'une vision exotisante et de l'ostracisme. Qu'il s'abord, elle enferme les Roms dans une figuration contrainte de la marginalité ou de l'errance, incapable d

Paris-Sud XI, Université de

247

Comparing exposure metrics for classifying ‘dangerous heat’ in heat wave and health warning systems  

Science Journals Connector (OSTI)

Heat waves have been linked to excess mortality and morbidity, and are projected to increase in frequency and intensity with a warming climate. This study compares exposure metrics to trigger heat wave and health warning systems (HHWS), and introduces a novel multi-level hybrid clustering method to identify potential dangerously hot days. Two-level and three-level hybrid clustering analysis as well as common indices used to trigger HHWS, including spatial synoptic classification (SSC), and the 90th, 95th, and 99th percentiles of minimum and relative minimum temperature (using a 10 day reference period), were calculated using a summertime weather dataset in Detroit from 1976 to 2006. The days classified as ‘hot’ with hybrid clustering analysis, SSC, minimum and relative minimum temperature methods differed by method type. SSC tended to include the days with, on average, 2.5 °C lower daily minimum temperature and 5.3 °C lower dew point than days identified by other methods. These metrics were evaluated by comparing their performance in predicting excess daily mortality. The 99th percentile of minimum temperature was generally the most predictive, followed by the three-level hybrid clustering method, the 95th percentile of minimum temperature, SSC and others. Our proposed clustering framework has more flexibility and requires less substantial meteorological prior information than the synoptic classification methods. Comparison of these metrics in predicting excess daily mortality suggests that metrics thought to better characterize physiological heat stress by considering several weather conditions simultaneously may not be the same metrics that are better at predicting heat-related mortality, which has significant implications in HHWSs.

Kai Zhang; Richard B. Rood; George Michailidis; Evan M. Oswald; Joel D. Schwartz; Antonella Zanobetti; Kristie L. Ebi; Marie S. O'Neill

2012-01-01T23:59:59.000Z

248

Pioneering Nuclear Waste Disposal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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

249

SRS - Programs - Waste Solidification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Solidification Waste Solidification The two primary facilities operated within the Waste Solidification program are Saltstone and the Defense Waste Processing Facility (DWPF). Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. The largest radioactive waste glassification plant in the world, DWPF converts the high-level liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for immobilizing high-level radioactive liquids into a more stable, manageable form until a federal

250

High level nuclear waste  

SciTech Connect (OSTI)

The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immobilization plant is to be the Defense Waste Processing Facility at Savannah River, scheduled for 1983 project submission to Congress and 1989 operation. Waste forms are still being selected for this plant. Borosilicate glass is currently the reference form, but alternate candidates include concretes, calcines, other glasses, ceramics, and matrix forms.

Crandall, J L

1980-01-01T23:59:59.000Z

251

Underground waste barrier structure  

DOE Patents [OSTI]

Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

252

Synthesizing Optimal Waste Blends  

Science Journals Connector (OSTI)

Vitrification of tank wastes to form glass is a technique that will be used for the disposal of high-level waste at Hanford. ... Durability restrictions ensure that the resultant glass meets the quantitative criteria for disposal/long-term storage in a repository. ... If glasses are formulated to minimize the volume of glass that would be produced, then the cost of processing the waste and storing the resultant glass would be greatly reduced. ...

Venkatesh Narayan; Urmila M. Diwekar; Mark Hoza

1996-10-08T23:59:59.000Z

253

Microsoft Word - DOE-EA-1707D_Revised_Predecisional_EA Closure_NRDWL-SWL08232011.docx  

Broader source: Energy.gov (indexed) [DOE]

7D 7D REVISED PREDECISIONAL DRAFT AUGUST 2011 Environmental Assessment Closure of Nonradioactive Dangerous Waste Landfill (NRDWL) and Solid Waste Landfill (SWL), Hanford Site, Richland, Washington U.S. Department of Energy Richland Operations Office Richland, Washington 99352 DOE/EA-1707D REVISED PREDECISIONAL DRAFT AUGUST 2011 DOE/EA-1707D REVISED PREDECISIONAL DRAFT iii AUGUST 2011 Contents 1 1 Introduction and Purpose and Need ............................................................................................. 1-1 2 1.1 Introduction ............................................................................................................................ 1-1 3 1.2 Purpose and Need ................................................................................................................... 1-2 4

254

Waste Confidence Discussion  

Broader source: Energy.gov (indexed) [DOE]

Long-Term Long-Term Waste Confidence Update Christine Pineda Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission National Transportation Stakeholders Forum May 2012 ♦ Knoxville, Tennessee Long-Term Update Draft Report, "Background and Preliminary Assumptions for an Environmental Impact Statement- Long-Term Waste Confidence Update" Elements of the Long-Term Update - Draft environmental impact statement - Draft Waste Confidence Decision - Proposed Waste Confidence Rule based on the EIS and Decision, if applicable 2 Overview of Draft Report Background and assumptions report is first step in process. Basic topics in the report are:

255

Norcal Waste Systems, Inc.  

SciTech Connect (OSTI)

Fact sheet describes the LNG long-haul heavy-duty trucks at Norcal Waste Systems Inc.'s Sanitary Fill Company.

Not Available

2002-12-01T23:59:59.000Z

256

Section 24: Waste Characterization  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Energy (DOE). 1995b. Transuranic Waste Baseline Inventory Report (Revision 2, December). DOECAO-95-1121. ERMS 531643. Carlsbad Area Office, Carlsbad, NM. PDF Author U.S....

257

Waste Heat Recovery  

Office of Environmental Management (EM)

DRAFT - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. Introduction to the TechnologySystem ......

258

Electronic Waste Transformation  

Science Journals Connector (OSTI)

Electronic Waste Transformation ... Instead, entrepreneurial individuals and small businesses recover valuable metals such as copper from obsolete equipment through activities such as burning. ...

CHERYL HOGUE

2012-04-01T23:59:59.000Z

259

Waste minimization assessment procedure  

SciTech Connect (OSTI)

Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative.

Kellythorne, L.L. (Centerior Energy, Cleveland, OH (United States))

1993-01-01T23:59:59.000Z

260

Vitrification of waste  

DOE Patents [OSTI]

A method is described for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300 C to 800 C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100 C to 1400 C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, G.G.

1999-04-06T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Avoidable waste management costs  

SciTech Connect (OSTI)

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

262

Waste Isolation Pilot Plant  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

September 19, 2014 - No second release at WIPP September 12, 2014 - Waste hoist transformer replacement September 09, 2014 - Additional areas cleared in WIPP underground...

263

Vitrification of waste  

DOE Patents [OSTI]

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300.degree. C. to 800.degree. C. to incinerate organic materials, then heated further to a temperature in the range of approximately 1100.degree. C. to 1400.degree. C. at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

264

ANL technical support program for DOE environmental restoration and waste management. Annual report, October 1993--September 1994  

SciTech Connect (OSTI)

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1994 on the following tasks: (1) Critical Reviews of important parameters that affect the reactivity of glass in an unsaturated environment are being prepared. (2) A series of tests is ongoing to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. (3) The effect of radiation upon the durability of waste glasses at a high SA/V ratio and a high gas-to-liquid volume ratio has been assessed. (4) A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SA/V ratios. Such differences in the SA/V ratio may significantly affect glass durability. At long-term periods and high SA/V ratios, acceleration in glass reaction has been observed. (5) Tests were initiated on West Valley Reference 6 (WV6) glass and on the Environmental Assessment (EA) glass. (6) Tests with the actinide-doped West Valley glass ATM-10 have been in progress for over seven years as a part of work for the Yucca Mountain Site Characterization Project (YMP). (7) Analytical electron microscopy (AEM) is being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Also, colloids from the leach solutions are being studied using AEM.

Bates, J.K.; Brown, N.R.; Buck, E.C. [and others

1995-06-01T23:59:59.000Z

265

Waste Loading Enhancements for Hanford Low-Activity Waste Glasses  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

WASTE LOADING ENHANCEMENTS FOR HANFORD LOW-ACTIVITY WASTE GLASSES Albert A. Kruger, Glass Scientist DOE-WTP Project Office Engineering Division US Department of Energy Richland,...

266

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

of a PA is to examine the final waste disposition at Hanford, such as waste in the tanks at C-Farm. Vince said the quest is to model waste movement over 10,000 years,...

267

Vitrification of Simulated Fernald K-65 Silo Waste at Low Temperature  

SciTech Connect (OSTI)

Vitrification is the technology that has been chosen to solidify approximately 15,500 tons of geologic mill tailings at the Fernald Environmental Management Project (FEMP) in Fernald, Ohio. The geologic mill tailings are residues from the processing of pitchlende ore during 1949-1958. These waste residues are contained in silos in Operable Unit 4 (OU4) at the FEMP facility. Operable Unit 4 is one of five operable units at the FEMP. Operating Unit 4 consists of four concrete storage silos and their contents. Silos 1 and 2 contain K-65 mill tailing residues and a bentonite cap, Silo 3 contains non-radioactive metal oxides, and Silo 4 is empty. The K-65 residues contain radium, uranium, uranium daughter products, and heavy metals such as lead and barium.The K-65 waste leaches lead at greater than 100 times the allowable Environmental Protection Agency (EPA) Resource, Conservation, and Recovery Act (RCRA) concentration limits when tested by the Toxic Characteristic Leaching Procedure (TCLP). Vitrification was chosen by FEMP as the preferred technology for the Silos 1, 2, 3 wastes because the final waste form met the following criteria: controls radon emanation, eliminates the potential for hazardous or radioactive constituents to migrate to the aquifer below FEMP, controls the spread of radioactive particulates, reduces leachability of metals and radiological constituents, reduces volume of final wasteform for disposal, silo waste composition is favorable to vitrification, will meet current and proposed RCRA TCLP leaching criteria Glasses that melt at 1350 degrees C were developed by Pacific Northwest National Laboratory (PNNL) and glasses that melt between 1150-1350 degrees C were developed by the Vitreous State Laboratory (VSL) for the K-65 silo wastes. Both crucible studies and pilot scale vitrification studies were conducted by PNNL and VSL. Subsequently, a Vitrification Pilot Plant (VPP) was constructed at FEMP capable of operating at temperatures up to 1450 degrees C. The VPP began operation on June 19, 1996. The VPP was used to test surrogate FEMP wastes at melt temperatures between 1130 degrees C and 1350 {degrees}C. The VPP failed on December 26, 1996 while processing surrogate waste. After the failure of the FEMP VPP, vitrification technology and glass chemistry were reevaluated. This report documents the glass formulation development for K-65 waste completed at SRTC in April, 1993 in conjunction with Associated Technical Consultants (ATC) of Toledo, Ohio. The glass developed for the FEMP was formulated in a lithia substituted soda-lime-silica (SLS) glass per the Savannah River Technology Center (SRTC) patented Lithia Additive Melting Process (LAMP)* to avoid problematic phase separation known to occur in the borosilicate glass system (MO-B{sub 2}O{sub 3}- SiO{sub 2}), where (MO = CaO, MgO, BaO, and PbO). Lime, MgO, BaO and PbO are all constituents of the FEMP wastes and thus subject to phase separation when vitrified in borosilicate glass. Phase separation is known to compromise waste glass stability. The SRTC soda-lithia-lime- silica (SLLS) glass melted at 1050 degrees C. Similar SLLS glass formulations have recently been demonstrated at the Oak Ridge Reservation (ORR) in a full scale melter with mixed (radioactive and hazardous) wastes.The low melting temperatures achieved with the SLLS glass minimize volatilization of hazardous species such as arsenic, lead, and selenium during vitrification. An 81 percent K-65 waste loading was demonstrated. The SRTC SLLS glass passed the Environmental Protection Agency (EPA) Toxic Characteristic Leach Procedure (TCLP) for all the hazardous constituents of concern under the current regulations. The SLLS glass is as durable as the high melting PNNL SLS glass and is more durable than the borosilicate glasses previously developed by VSL for the K-65 wastes.

Jantzen, C.M. [Westinghouse Savannah River Company, AIKEN, SC (United States); Pickett, J.B.

1998-01-14T23:59:59.000Z

268

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network [OSTI]

DESCRIPTION DETAILS * Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission lives. Radioactive Waste generated through wet chemistry Waste Minimization 30 Mixed waste / Liquid

269

Chapter 19 - Nuclear Waste Fund  

Broader source: Energy.gov (indexed) [DOE]

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

270

Solid Waste Rules (New Hampshire)  

Broader source: Energy.gov [DOE]

The solid waste statute applies to construction and demolition debris, appliances, recyclables, and the facilities that collect, process, and dispose of solid waste. DES oversees the management of...

271

Solid Waste Management (North Carolina)  

Broader source: Energy.gov [DOE]

The Solid Waste Program regulates safe management of solid waste through guidance, technical assistance, regulations, permitting, environmental monitoring, compliance evaluation and enforcement....

272

Waste Management | Department of Energy  

Energy Savers [EERE]

Management Waste Management Oak Ridge has an onsite CERCLA disposal facility, the Environmental Management Waste Management Facility, that reduces cleanup and transportation costs....

273

Municipal Waste Combustion (New Mexico)  

Broader source: Energy.gov [DOE]

This rule establishes requirements for emissions from, and design and operation of, municipal waste combustion units. "Municipal waste" means all materials and substances discarded from residential...

274

Waste Disposal | Department of Energy  

Office of Environmental Management (EM)

Disposal Waste Disposal Trucks transport debris from Oak Ridges cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility....

275

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

276

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

277

Nuclear waste solutions  

DOE Patents [OSTI]

High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

278

Radioactive waste storage issues  

SciTech Connect (OSTI)

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

279

A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository  

SciTech Connect (OSTI)

The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple sources to compile the potential transportation impacts presented in the Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DEIS). The database uses the results from existing models and codes such as RADTRAN, RISKIND, INTERLINE, and HIGHWAY to estimate transportation-related impacts of transporting spent nuclear fuel and high-level radioactive waste from commercial reactors and U. S. Department of Energy (DOE) facilities to Yucca Mountain. The source tables in the database are compendiums of information from many diverse sources including: radionuclide quantities for each waste type; route and route characteristics for rail, legal-weight truck, heavy haul. truck, and barge transport options; state-specific accident and fatality rates for routes selected for analysis; packaging and shipment data by waste type; unit risk factors; the complex behavior of the packaged waste forms in severe transport accidents; and the effects of exposure to radiation or the isotopic specific effects of radionclides should they be released in severe transportation accidents. The database works together with the codes RADTRAN (Neuhauser, et al, 1994) and RISKlND (Yuan, et al, 1995) to calculate incident-free dose and accident risk. For the incident-free transportation scenario, the database uses RADTRAN and RISKIND-generated data to calculate doses to offlink populations, onlink populations, people at stops, crews, inspectors, workers at intermodal transfer stations, guards at overnight stops, and escorts, as well as non-radioactive pollution health effects. For accident scenarios, the database uses RADTRAN-generated data to calculate dose risks based on ingestion, inhalation, resuspension, immersion (cloudshine), and groundshine as well as non-radioactive traffic fatalities. The Yucca Mountain EIS Transportation Database was developed using Microsoft Access 97{trademark} software and the Microsoft Windows NT{trademark} operating system. The database consists of tables for storing data, forms for selecting data for querying, and queries for retrieving the data in a predefined format. Database queries retrieve records based on input parameters and are used to calculate incident-free and accident doses using unit risk factors obtained from RADTRAN results. The next section briefly provides some background that led to the development of the database approach used in preparing the Yucca Mountain DEIS. Subsequent sections provide additional details on the database structure and types of impacts calculated using the database.

Ralph Best; T. Winnard; S. Ross; R. Best

2001-08-17T23:59:59.000Z

280

Pioneering Nuclear Waste Disposal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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 DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Salt Waste Processing Initiatives  

Broader source: Energy.gov (indexed) [DOE]

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

282

HLW Glass Waste Loadings  

Broader source: Energy.gov (indexed) [DOE]

HLW HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC Overview Overview  Vitrification - general background  Joule heated ceramic melter (JHCM) technology  Factors affecting waste loadings  Waste loading requirements and projections  WTP DWPF  DWPF  Yucca Mountain License Application requirements on waste loading  Summary Vitrification  Immobilization of waste by conversion into a glass  Internationally accepted treatment for HLW  Why glass?  Amorphous material - able to incorporate a wide spectrum of elements over wide ranges of composition; resistant to radiation damage  Long-term durability - natural analogs Relatively simple process - amenable to nuclearization at large  Relatively simple process - amenable to nuclearization at large scale  There

283

DEMONSTRATION OF THE NEXT-GENERATION CAUSTIC-SIDE SOLVENT EXTRACTION SOLVENT WITH 2-CM CENTRIFUGAL CONTRACTORS USING TANK 49H WASTE AND WASTE SIMULANT  

SciTech Connect (OSTI)

Researchers successfully demonstrated the chemistry and process equipment of the Caustic-Side Solvent Extraction (CSSX) flowsheet using MaxCalix for the decontamination of high level waste (HLW). The demonstration was completed using a 12-stage, 2-cm centrifugal contactor apparatus at the Savannah River National Laboratory (SRNL). This represents the first CSSX process demonstration of the MaxCalix solvent system with Savannah River Site (SRS) HLW. Two tests lasting 24 and 27 hours processed non-radioactive simulated Tank 49H waste and actual Tank 49H HLW, respectively. Conclusions from this work include the following. The CSSX process is capable of reducing {sup 137}Cs in high level radioactive waste by a factor of more than 40,000 using five extraction, two scrub, and five strip stages. Tests demonstrated extraction and strip section stage efficiencies of greater than 93% for the Tank 49H waste test and greater than 88% for the simulant waste test. During a test with HLW, researchers processed 39 liters of Tank 49H solution and the waste raffinate had an average decontamination factor (DF) of 6.78E+04, with a maximum of 1.08E+05. A simulant waste solution ({approx}34.5 liters) with an initial Cs concentration of 83.1 mg/L was processed and had an average DF greater than 5.9E+03, with a maximum DF of greater than 6.6E+03. The difference may be attributable to differences in contactor stage efficiencies. Test results showed the solvent can be stripped of cesium and recycled for {approx}25 solvent turnovers without the occurrence of any measurable solvent degradation or negative effects from minor components. Based on the performance of the 12-stage 2-cm apparatus with the Tank 49H HLW, the projected DF for MCU with seven extraction, two scrub, and seven strip stages operating at a nominal efficiency of 90% is {approx}388,000. At 95% stage efficiency, the DF in MCU would be {approx}3.2 million. Carryover of organic solvent in aqueous streams (and aqueous in organic streams) was less than 0.1% when processing Tank 49H HLW. The entrained solvent concentration measured in the decontaminated salt solution (DSS) was as much as {approx}140 mg/L, although that value may be overstated by as much as 50% due to modifier solubility in the DSS. The entrained solvent concentration was measured in the strip effluent (SE) and the results are pending. A steady-state concentration factor (CF) of 15.9 was achieved with Tank 49H HLW. Cesium distribution ratios [D(Cs)] were measured with non-radioactive Tank 49H waste simulant and actual Tank 49H waste. Below is a comparison of D(Cs) values of ESS and 2-cm tests. Batch Extraction-Strip-Scrub (ESS) tests yielded D(Cs) values for extraction of {approx}81-88 for tests with Tank 49H waste and waste simulant. The results from the 2-cm contactor tests were in agreement with values of 58-92 for the Tank 49H HLW test and 54-83 for the simulant waste test. These values are consistent with the reference D(Cs) for extraction of {approx}60. In tests with Tank 49H waste and waste simulant, batch ESS tests measured D(Cs) values for the two scrub stages as {approx}3.5-5.0 for the first scrub stage and {approx}1.0-3.0 for the second scrub stage. In the Tank 49H test, the D(Cs) values for the 2-cm test were far from the ESS values. A D(Cs) value of 161 was measured for the first scrub stage and 10.8 for the second scrub stage. The data suggest that the scrub stage is not operating as effectively as intended. For the simulant test, a D(Cs) value of 1.9 was measured for the first scrub stage; the sample from the second scrub stage was compromised. Measurements of the pH of all stage samples for the Tank 49H test showed that the pH for extraction and scrub stages was 14 and the pH for the strip stages was {approx}7. It is expected that the pH of the second scrub stage would be {approx}12-13. Batch ESS tests measured D(Cs) values for the strip stages to be {approx}0.002-0.010. A high value in Strip No.3 of a test with simulant solution has been attributed to issues associated with the limits of detection for the

Pierce, R.; Peters, T.; Crowder, M.; Caldwell, T.; Pak, D; Fink, S.; Blessing, R.; Washington, A.

2011-09-27T23:59:59.000Z

284

Round-robin testing of a reference glass for low-activity waste forms  

SciTech Connect (OSTI)

A round robin test program was conducted with a glass that was developed for use as a standard test material for acceptance testing of low-activity waste glasses made with Hanford tank wastes. The glass is referred to as the low-activity test reference material (LRM). The program was conducted to measure the interlaboratory reproducibility of composition analysis and durability test results. Participants were allowed to select the methods used to analyze the glass composition. The durability tests closely followed the Product Consistency Test (PCT) Method A, except that tests were conducted at both 40 and 90 C and that parallel tests with a reference glass were not required. Samples of LRM glass that had been crushed, sieved, and washed to remove fines were provided to participants for tests and analyses. The reproducibility of both the composition and PCT results compare favorably with the results of interlaboratory studies conducted with other glasses. From the perspective of reproducibility of analysis results, this glass is acceptable for use as a composition standard for nonradioactive components of low-activity waste forms present at >0.1 elemental mass % and as a test standard for PCTS at 40 and 90 C. For PCT with LRM glass, the expected test results at the 95% confidence level are as follows: (1) at 40 C: pH = 9.86 {+-} 0.96; [B] = 2.30 {+-} 1.25 mg/L; [Na] = 19.7 {+-} 7.3 mg/L; [Si] = 13.7 {+-} 4.2 mg/L; and (2) at 90 C: pH = 10.92 {+-} 0.43; [B] = 26.7 {+-} 7.2 mg/L; [Na] = 160 {+-} 13 mg/L; [Si] = 82.0 {+-} 12.7 mg/L. These ranges can be used to evaluate the accuracy of PCTS conducted at other laboratories.

Ebert, W. L.; Wolf, S. F.

1999-12-06T23:59:59.000Z

285

REAL WASTE TESTING OF SPHERICAL RESORCINOL-FORMALDEHYDE ION EXCHANGE RESIN  

SciTech Connect (OSTI)

This report presents data on batch contact and column testing tasks for spherical resorcinol-formaldehyde (sRF) resin. The testing used a non-radioactive simulant of SRS Tank 2F dissolved salt, as well as an actual radioactive waste sample of similar composition, which are both notably high in sodium (6 M). The resin was Microbeads batch 5E-370/641 which had been made on the hundred gallon scale. Equilibrium batch contact work focused on cesium at a temperature of 25 C due to the lack of such data to better benchmark existing isotherm models. Two campaigns were performed with small-scale ion exchange columns, first with Tank 2F simulant, then with actual dissolved salt in the Shielded Cells. An extrapolation of the batch contact results with radioactive waste over-predicted the cesium loaded onto the IX sRF resin bed by approximately 11%. This difference is not unexpected considering uncertainties from measurement and extrapolation and because the ion exchange that occurs when waste flows through a resin bed probably cannot reach the same level of equilibrium as when waste and resin are joined in a long term batch contact. Resin was also characterized to better understand basic chemistry issues such as holdup of trace transition metals present in the waste feed streams. The column tests involved using two beds of sRF resin in series, with the first bed referred to as the Lead column and the second bed as the Lag column. The test matrix included two complete IX cycles for both the simulant and actual waste phases. A cycle involves cesium adsorption, until the resin in the Lead column reaches saturation, and then regenerating the sRF resin, which includes eluting the cesium. Both the simulated and the actual wastes were treated with two cycles of operation, and the resin beds that were used in the Lead and Lag columns of simulant test phase were regenerated and reused in the actual waste test phase. This task is the first to demonstrate the treatment of SRS waste with sRF resin and the tests clearly demonstrated cesium decontamination for actual waste. The results of the column tests were similar for both the simulated and the actual waste and demonstrated Cs removal with sRF from both wastes. For a flowrate of 1.4 bed volumes (BV)/hour at 25 C those results with sRF resin were: (1) Simulant and actual waste results are equivalent; (2) Cs breakthrough began between 200 and 250 BV; (3) Cs breakthrough reached 100% at around 400 BV; (4) Cs breakthrough curve from 5% to 100% is approximately linear; (5) Cs elution with 0.5 M HNO3 starts at 2 BV and ends at 6BV; (6) Most, if not all, of Cs adsorbed during treatment is released during elution; (7) At 100% breakthrough of Cs the resin bed adsorbs approximately 85% of full capacity before detection in the effluent; the remaining 15% is adsorbed at saturation; (8) Approximately 90% of resin bed changes (color and volume) are complete by 6 BV; and (9) During elution the resin shrinks to about 80% of its fully working (sodium form) BV.

Nash, C.; Duignan, M.

2009-10-30T23:59:59.000Z

286

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill  

E-Print Network [OSTI]

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill Timothy D. Stark, F.ASCE1 landfills may contain aluminum from residential and commercial solid waste, industrial waste, and aluminum, may react with liquid in a landfill and cause uncontrolled temperature increases, significant changes

287

Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities  

Broader source: Energy.gov (indexed) [DOE]

0: Solid Waste Management 0: Solid Waste Management Facilities (New York) Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities (New York) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Institutional Investor-Owned Utility Multi-Family Residential Municipal/Public Utility Rural Electric Cooperative Transportation Utility Program Info State New York Program Type Environmental Regulations Provider NY Department of Environmental Conservation These regulations apply to all solid wastes with the exception of hazardous or radioactive waste. Proposed solid waste processing facilities are required to obtain permits prior to construction, and the regulations provide details about permitting, construction, registration, and operation requirements. The regulations contain specific guidance for land

288

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect (OSTI)

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

289

Waste inspection tomography (WIT)  

SciTech Connect (OSTI)

The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented.

Bernardi, R.T.; Han, K.S.

1994-12-31T23:59:59.000Z

290

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

291

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

292

Hazardous Waste Disposal Sites (Iowa)  

Broader source: Energy.gov [DOE]

These sections contain information on fees and monitoring relevant to operators of hazardous waste disposal sites.

293

Generating power with waste wood  

SciTech Connect (OSTI)

Among the biomass renewables, waste wood has great potential with environmental and economic benefits highlighting its resume. The topics of this article include alternate waste wood fuel streams; combustion benefits; waste wood comparisons; waste wood ash; pilot scale tests; full-scale test data; permitting difficulties; and future needs.

Atkins, R.S.

1995-02-01T23:59:59.000Z

294

Methane generation from waste materials  

DOE Patents [OSTI]

An organic solid waste digester for producing methane from solid waste, the digester comprising a reactor vessel for holding solid waste, a sprinkler system for distributing water, bacteria, and nutrients over and through the solid waste, and a drainage system for capturing leachate that is then recirculated through the sprinkler system.

Samani, Zohrab A. (Las Cruces, NM); Hanson, Adrian T. (Las Cruces, NM); Macias-Corral, Maritza (Las Cruces, NM)

2010-03-23T23:59:59.000Z

295

Public Resistance is Waste-Based and What to Do About That - 13412  

SciTech Connect (OSTI)

'Nuclear Communicators' connect a highly advanced sci-tech world with the world of everyday living. One challenge is helping stakeholders fit together three Big Ideas: (1) the valuable nuclear energy resource, (2) nuclear energy's invisible mortal dangers and potential bad-guy threats, and (3) critical scientific and engineering knowledge that is far over the heads of average (grade 8) USA reading levels. This article provides an overview of what does - and does not - work in our public communications. What does not work: 1. Going off topic. Address what concerns people most: how to manage nuclear wastes. 2. Underestimating public intelligence. What works: 1. Doing your homework on community history regarding nuclear materials. 2. Having discussion forums and public meetings with special guests from industry, government, and local leaders. 3. Regular cycles of communication with community groups to build a long-term dialogue. Solutions to some communication challenges require handling four gaps and one jungle: 1. Facts gap - Honest information about waste disposition. 2. Time gap - The timelines associated with waste management include 300 years, 10,000 years, and 703.8 million years. How do we talk about this? 3. Money gap - Who pays for new waste management challenges and technologies? 4. Confidence gap - Link local options to regional, national, and global knowledge. 5. Decision jungle - How can we make waste management rules and infrastructure more logical and transparent? Public communication needs to be grounded in facts for people who want to be credible actors in the new nuclear world. (authors)

Ford, Laurie [Critical Path Consultants, 3101 Splitrock Road, Columbus Ohio 43221 (United States)] [Critical Path Consultants, 3101 Splitrock Road, Columbus Ohio 43221 (United States)

2013-07-01T23:59:59.000Z

296

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect (OSTI)

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

297

A mechanism for providing institutional assurance for the safe handling of acutely toxic or physically dangerous chemicals in research laboratories  

Science Journals Connector (OSTI)

Chemical use is ubiquitous in research laboratories and is necessary for the advancement of research and creation of new technology. Regulatory mechanisms currently exist that mandate the provision of basic safety training for workers and the assurance that essential safety information is readily available. Unfortunately, in some cases, institutional oversight of specific “high risk” laboratory chemical use may be absent. This may be due in part to the difficulty in delineating between chemicals that are commonly used but possess a hazardous characteristic (e.g., flammability) and those that exhibit acutely toxic or particularly dangerous properties (e.g., explosivity). In 1994, The University of Texas Health Science Center at Houston began addressing this issue through the creation of an institutional Chemical Safety Committee (CSC) that consists largely of research faculty. Through a shared governance process, the committee identified criteria for which certain chemical use would require institutional review and approval, striving to achieve a balance between supporting research while providing an added level of assurance that work involving the acutely toxic or physically dangerous chemical can be performed safely. The process used for developing these criteria is described along with the lessons learned from its evolutionary process.

Robert Emery

2013-01-01T23:59:59.000Z

298

Health Care Professionals vs Other Professionals: Do They Have Different Perceptions about Health Care Waste and Dangerous Products Pictograms? Some Findings Using a Digital Device in Field Survey  

Science Journals Connector (OSTI)

This paper presents a part of a wider research about GHS symbols comprehensibility. Here, a field survey was conducted using a digital device, instead of traditional platform – printed paper. Participants were...

Cláudia Renata Mont’Alvão

2014-01-01T23:59:59.000Z

299

Tank Waste Strategy Update  

Broader source: Energy.gov (indexed) [DOE]

Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

300

Waste Steam Recovery  

E-Print Network [OSTI]

An examination has been made of the recovery of waste steam by three techniques: direct heat exchange to process, mechanical compression, and thermocompression. Near atmospheric steam sources were considered, but the techniques developed are equally...

Kleinfeld, J. M.

1979-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Waste and Recycling  

ScienceCinema (OSTI)

Nuclear engineer Dr. Kathy McCarthy talks about nuclear energy, the challenge of nuclear waste and the research aimed at solutions. For more information about nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

McCarthy, Kathy

2013-05-28T23:59:59.000Z

302

Oxidative Alkaline leaching of Americium from simulated high-level nuclear waste sludges  

SciTech Connect (OSTI)

Oxidative alkaline leaching has been proposed to pre-treat the high-level nuclear waste sludges to remove some of the problematic (e.g., Cr) and/or non-radioactive (e.g., Na, Al) constituents before vitrification. It is critical to understand the behavior of actinides, americium and plutonium in particular, in oxidative alkaline leaching. We have studied the leaching behavior of americium from four different sludge simulants (BiPO{sub 4}, BiPO{sub 4 modified}, Redox, PUREX) using potassium permanganate and potassium persulfate in alkaline solutions. Up to 60% of americium sorbed onto the simulants is leached from the sludges by alkaline persulfate and permanganate. The percentage of americium leached increases with [NaOH] (between 1.0 and 5.0 M). The initial rate of americium leaching by potassium persulfate increases in the order BiPO{sub 4} sludge < Redox sludge < PUREX sludge. The data are most consistent with oxidation of Am{sup 3+} in the sludge to either AmO{sub 2}{sup +} or AmO{sub 2}{sup 2+} in solution. Though neither of these species is expected to exhibit long-term stability in solution, the potential for mobilization of americium from sludge samples would have to be accommodated in the design of any oxidative leaching process for real sludge samples.

Reed, Wendy A.; Garnov, Alexander Yu.; Rao, Linfeng; Nash, Kenneth L.; Bond, Andrew H.

2004-01-23T23:59:59.000Z

303

Citrus Waste Biomass Program  

SciTech Connect (OSTI)

Renewable Spirits is developing an innovative pilot plant bio-refinery to establish the commercial viability of ehtanol production utilizing a processing waste from citrus juice production. A novel process based on enzymatic hydrolysis of citrus processing waste and fermentation of resulting sugars to ethanol by yeasts was successfully developed in collaboration with a CRADA partner, USDA/ARS Citrus and Subtropical Products Laboratory. The process was also successfully scaled up from laboratory scale to 10,000 gal fermentor level.

Karel Grohman; Scott Stevenson

2007-01-30T23:59:59.000Z

304

Independent Activity Report, Hanford Waste Treatment Plant -...  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment Plant - February 2011 Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality...

305

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

Glasses Developed for Nuclear Waste Immobilization," 91[12],solubility in borosilicate nuclear waste glass Ashutoshfor the researchers in nuclear waste community around the

McCloy, John S.

2014-01-01T23:59:59.000Z

306

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))...

307

Municipal Solid Waste | Open Energy Information  

Open Energy Info (EERE)

Waste Jump to: navigation, search TODO: Add description List of Municipal Solid Waste Incentives Retrieved from "http:en.openei.orgwindex.php?titleMunicipalSolidWaste&oldid...

308

Waste Processing Annual Technology Development Report 2007 |...  

Office of Environmental Management (EM)

Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007...

309

Pollution Prevention, Waste Reduction, and Recycling | Department...  

Office of Environmental Management (EM)

Pollution Prevention, Waste Reduction, and Recycling Pollution Prevention, Waste Reduction, and Recycling The Pollution Prevention, Waste Reduction and Recycling Program was...

310

Waste Isolation Pilot Plant | Department of Energy  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Operators prepare drums of contact-handled transuranic waste for loading into transportation containers Operators prepare...

311

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

312

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Broader source: Energy.gov (indexed) [DOE]

Municipal Waste Planning, Recycling and Waste Reduction Act Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Pennsylvania Program Type Environmental Regulations

313

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT  

SciTech Connect (OSTI)

This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

CRAWFORD TW

2008-07-17T23:59:59.000Z

314

Energy from waste via coal/waste co-firing  

SciTech Connect (OSTI)

The paper reviews the feasibility of waste-to-energy plants using the cocombustion of coal with refuse-derived fuels. The paper discusses the types of wastes available: municipal solid wastes, plastics, tires, biomass, and specialized industrial wastes, such as waste oils, post-consumer carpet, auto shredder residues, and petroleum coke. The five most common combustion systems used in co-firing are briefly described. They are the stoker boiler, suspension-fired boilers, cyclone furnaces, fluidized bed boilers, and cement kilns. The paper also discusses the economic incentives for generating electricity from waste.

Winslow, J.; Ekmann, J.; Smouse, S. [Dept. of Energy, Pittsburgh, PA (United States). Pittsburgh Energy Technology Center; Ramezan, M. [Burns and Roe Services Corp., Pittsburgh, PA (United States); Harding, S.

1996-12-31T23:59:59.000Z

315

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

316

LANL reaches waste shipment milestone  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

317

The largest radioactive waste glassification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

318

Waste Treatment Plant - 12508  

SciTech Connect (OSTI)

The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration equipment, cesium-ion exchange columns, evaporator boilers and recirculation pumps, and various mechanical process pumps for transferring process fluids. During the first phase of pretreatment, the waste will be concentrated using an evaporation process. Solids will be filtered out, and the remaining soluble, highly radioactive isotopes will be removed using an ion-exchange process. The high-level solids will be sent to the High-Level Waste (HLW) Vitrification Facility, and the low activity liquids will be sent to the Low-Activity Waste (LAW) Vitrification Facility for further processing. The high-level waste will be transferred via underground pipes to the HLW Facility from the Pretreatment Facility. The waste first arrives at the wet cell, which rests inside a black-cell area. The pretreated waste is transferred through shielded pipes into a series of melter preparation and feed vessels before reaching the melters. Liquids from various facility processes also return to the wet cell for interim storage before recycling back to the Pretreatment Facility. (authors)

Harp, Benton; Olds, Erik [US DOE (United States)

2012-07-01T23:59:59.000Z

319

Mixed waste characterization reference document  

SciTech Connect (OSTI)

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

NONE

1997-09-01T23:59:59.000Z

320

Hazardous Waste/Mixed Waste Treatment Building throughput study  

SciTech Connect (OSTI)

The hazardous waste/mixed waste HW/MW Treatment Building (TB) is the specified treatment location for solid hazardous waste/mixed waste at SRS. This report provides throughput information on the facility based on known and projected waste generation rates. The HW/MW TB will have an annual waste input for the first four years of approximately 38,000 ft{sup 3} and have an annual treated waste output of approximately 50,000 ft{sup 3}. After the first four years of operation it will have an annual waste input of approximately 16,000 ft{sup 3} and an annual waste output of approximately 18,000 ft. There are several waste streams that cannot be accurately predicted (e.g. environmental restoration, decommissioning, and decontamination). The equipment and process area sizing for the initial four years should allow excess processing capability for these poorly defined waste streams. A treatment process description and process flow of the waste is included to aid in understanding the computations of the throughput. A description of the treated wastes is also included.

England, J.L.; Kanzleiter, J.P.

1991-12-18T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

1995 Report on Hanford site land disposal restrictions for mixed waste  

SciTech Connect (OSTI)

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated 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 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report.

Black, D.G.

1995-04-01T23:59:59.000Z

322

Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126  

SciTech Connect (OSTI)

Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it was used for the column testing to obtain breakthrough curves under various conditions of pH and brine concentration. The breakthrough point had a dependency on pH and the brine concentration. We found that when the pH was higher or the brine concentration was lower, the longer it took to reach the breakthrough point. The inhibition of strontium adsorption by alkali earth metals would be diminished for conditions of higher pH and lower brine concentration. (authors)

Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan)] [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan); Asano, Takashi; Tamata, Shin [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)] [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)

2013-07-01T23:59:59.000Z

323

Waste generator services implementation plan  

SciTech Connect (OSTI)

Recurring waste management noncompliance problems have spurred a fundamental site-wide process revision to characterize and disposition wastes at the Idaho National Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will streamline the waste acceptance process and provide waste generators comprehensive waste management services through a single, accountable organization to manage and disposition wastes in a timely, cost-effective, and compliant manner. This report outlines the strategy for implementing Waste Generator Services across the INEEL. It documents the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project team since October 1997. These efforts have included defining problems associated with the INEEL waste management process; identifying commercial best management practices; completing a review of DOE Complex-wide waste management training requirements; and involving others through an Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and WGS organization. The report defines the work that will be performed by Waste Generator Services, the organization and resources, the waste acceptance process flow, the funding approach, methods for measuring performance, and the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL facilities in a phased approach, with implementation completed by March 1999.

Mousseau, J.; Magleby, M.; Litus, M.

1998-04-01T23:59:59.000Z

324

Transuranic Waste Tabletop  

Broader source: Energy.gov (indexed) [DOE]

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

325

Pioneering Nuclear Waste Disposal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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

326

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN  

E-Print Network [OSTI]

;Canadian Energy-From-Waste Coalition (CEFWC) 1 There is considerable merit to the ideas outlined commitment to foster a green and sustainable economy. The Canadian Energy-From-Waste Coalition (CEFWC sign that the system is failing. #12;Canadian Energy-From-Waste Coalition (CEFWC) 2 Like you, the CEFWC

Columbia University

327

Waste IncIneratIon and Waste PreventIon  

E-Print Network [OSTI]

disposing of waste, it also makes consider- able amounts of energy available in the form of electricity emissions annu- ally. About 50 percent of the energy contained in residual municipal waste comes from- sions from the fossil waste fraction and the fos- sil energy purchased from external sources

328

Skutterudite Thermoelectric Generator For Automotive Waste Heat...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite TE modules were...

329

Waste Heat Recovery Opportunities for Thermoelectric Generators...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Waste Heat Recovery Opportunities for Thermoelectric Generators Waste Heat Recovery Opportunities for Thermoelectric Generators Thermoelectrics have unique advantages for...

330

High-Level Waste Requirements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The guide provides the criteria for determining which DOE radioactive wastes are to be managed as high-level waste in accordance with DOE M 435.1-1.

1999-07-09T23:59:59.000Z

331

Pathology waste includes: Transgenic animals.  

E-Print Network [OSTI]

resistant, have tight fitting covers, be clean, and in good repair. · Pathology waste must be transferred via the Internet: · Visit www.ehs.uci.edu/programs/enviro/. · Fill out the "Biomedical Waste

George, Steven C.

332

Waste Management Coordinating Lead Authors  

E-Print Network [OSTI]

-use and recycling ..............602 10.4.6 Wastewater and sludge treatment.....................602 10.4.7 Waste ............................................591 10.2.2 Wastewater generation ....................................592 10.2.3 Development trends for waste and ......................... wastewater ......................................................593

Columbia University

333

Leaching of Nuclear Waste Glasses  

Science Journals Connector (OSTI)

Resistance to aqueous corrosion is the most important requirement of glasses designed to immobilize high level radioactive wastes. Obtaining a highly durable nuclear waste glass is complicated by the requirement ...

L. L. Hench

1985-01-01T23:59:59.000Z

334

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

When did man discover nuclear waste? To answer this question, we first have to ask if nuclear waste really is something that could be called ... Prize in physics. In early writings within nuclear energy research ...

Göran Sundqvist

2002-01-01T23:59:59.000Z

335

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

336

Hydrothermal Processing of Wet Wastes  

Broader source: Energy.gov [DOE]

Breakout Session 3A—Conversion Technologies III: Energy from Our Waste—Will we Be Rich in Fuel or Knee Deep in Trash by 2025? Hydrothermal Processing of Wet Wastes James R. Oyler, President, Genifuel Corporation

337

Delaware Solid Waste Authority (Delaware)  

Broader source: Energy.gov [DOE]

The Delaware Solid Waste Authority (DSWA) runs three landfills, all of which recover methane and generate electricity with a total capacity of 24 MWs. The DSWA Solid Waste Plan includes goals,...

338

Explosive Waste Treatment Facility  

Broader source: Energy.gov (indexed) [DOE]

106 106 Environment a 1 Assessment for th.e Explosive Waste Treatment Facility at Site 300 Lawrence Livermore National Laboratory MASTER November 1995 U.S. Department of Energy Office of Environmental Restoration and Waste Management Washington, DOC. 20585 Portions of this document maly be illegible in electronic image products. Images are produced from the best available original document. Table of Contents 1 . 0 2.0 3 . 0 4.0 5 . 0 6.0 7 . 0 8 . 0 Document Summary .............................................................. 1 Purpose and Need for Agency Action ............................................. 3 Description of the Proposed Action and Alternatives ............................ 4 3.1.1 Location ............................................................. 4

339

Waste Isolation Pilot Plant  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE _______________ ) ) ss: __________________ COUNTY OF _____________ ) That I, ________________________, am the _________________________ (Indicate relationship) of ___________________________, who is deceased and make the attached request pursuant to 10 CFR, Section 1008. That the information contained on the attached request is true and correct to the best of my knowledge and belief, and I am signing this authorization subject to the penalties provided in 18 U.S.C. 1001. ____________________________ SIGNATURE NOTARIZATION: SUBSCRIBED and SWORN to before me this ______day of __________, 20_____

340

Converter waste disposal study  

SciTech Connect (OSTI)

The importance of waste management and disposal issues to the converting and print industries is demonstrated by the high response rate to a survey of US and Canadian converters and printers. The 30-item questionnaire measured the impact of reuse, recycling, source reduction, incineration, and landfilling on incoming raw-material packaging, process scrap, and waste inks, coatings, and adhesives. The results indicate that significant amounts of incoming packaging materials are reused in-house or through supplier take-back programs. However, there is very little reuse of excess raw materials and process scrap, suggesting the need for greater source reduction within these facilities as the regulatory climate becomes increasingly restrictive.

Schultz, R.B. (RBS Technologies, Inc., Skokie, IL (United States))

1993-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

WORLDWIDE FOCUS ON NUCLEAR WASTE  

Science Journals Connector (OSTI)

WORLDWIDE FOCUS ON NUCLEAR WASTE ... Volume grows and years pile up, but world lacks consensus on disposing of nuclear waste ... WHAT TO DO WITH SPENT nuclear fuel and high-level radioactive waste is a problem shared by much of the world. ...

JEFF JOHNSON

2001-06-18T23:59:59.000Z

342

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING  

E-Print Network [OSTI]

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING EFFICIENCY.EFFICIENCY. A l GA leaner Green #12 t R li Management Recycling Staff The Office of Waste Reduction & Recycling started in The Office of Waste Reduction & Recycling started in 1990, we have 14 full time staff positions. ·We collect over 40

Howitt, Ivan

343

Mixed Waste Working Group report  

SciTech Connect (OSTI)

The treatment of mixed waste remains one of this country`s most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country`s largest mixed waste generator, responsible for 95 percent of the Nation`s mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE`s earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies.

Not Available

1993-11-09T23:59:59.000Z

344

Waste-to-Energy Workshop  

Broader source: Energy.gov [DOE]

The Waste to Energy Roadmapping Workshop was held on November 5, 2014, in Arlington, Virginia. This workshop gathered waste-to-energy experts to identify the key technical barriers to the commercial deployment of liquid transportation fuels from wet waste feedstocks.

345

Danger of Tunnels on Al Aqsa Mosque Buildings For more than 40 years, the city of Jerusalem has faced accelerated historical transformation on  

E-Print Network [OSTI]

Danger of Tunnels on Al Aqsa Mosque Buildings Abstract For more than 40 years, the city tunnels under Al Aqsa Mosque and the Arab historical town to weaken the foundation of buildings. This research highlights Palestinian, Israeli and international important reports about the excavations under Al

346

Disposal of Nuclear Wastes  

Science Journals Connector (OSTI)

...generated between now and A.D. 2000 is about 0.04 km3 (0.01...high-level wastes do not be-come a public hazard. The AEC adopts this...pre-sented at the 66th national meeting of the American Institute of...ARH-SA-41 (Atlantic Richfield Hanford Co., Richland, Washington...

Arthur S. Kubo; David J. Rose

1973-12-21T23:59:59.000Z

347

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A

1999-07-09T23:59:59.000Z

348

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

Broader source: Energy.gov (indexed) [DOE]

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

349

Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode  

Broader source: Energy.gov (indexed) [DOE]

Regulation No. 8 - Solid Waste Composting Facilities Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Management Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for composting facilities. Operational requirements for putrescible waste facilities include siting, distance, and buffer requirements, as well as standards for avoiding harm to endangered species and contamination of air and water sources. Specific

350

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network [OSTI]

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

351

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect (OSTI)

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

352

Waste acceptance and waste loading for vitrified Oak Ridge tank waste  

SciTech Connect (OSTI)

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC`s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC.

Harbour, J.R.; Andrews, M.K.

1997-06-06T23:59:59.000Z

353

Environmental waste disposal contracts awarded  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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

354

Waste Isolation Pilot Plant - Reports  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

355

Waste Management | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Management Management Waste Management Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing The Department has approximately 88 million gallons of liquid waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

356

Process Waste Assessment, Mechanics Shop  

SciTech Connect (OSTI)

This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Mechanics Shop. The Mechanics Shop maintains and repairs motorized vehicles and equipment on the SNL/California site, to include motorized carts, backhoes, street sweepers, trash truck, portable emergency generators, trencher, portable crane, and man lifts. The major hazardous waste streams routinely generated by the Mechanics Shop are used oil, spent off filters, oily rags, and spent batteries. The used off and spent off filters make up a significant portion of the overall hazardous waste stream. Waste oil and spent batteries are sent off-site for recycling. The rags and spent on filters are not recycled. They are disposed of as hazardous waste. Mechanics Shop personnel continuously look for opportunities to minimize hazardous wastes.

Phillips, N.M.

1993-05-01T23:59:59.000Z

357

Waste Management | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Cleanup » Waste Management Cleanup » Waste Management Waste Management November 12, 2013 U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada. September 24, 2013 Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and

358

WASTE/BY-PRODUCT HYDROGEN DOE/DOD Workshop  

E-Print Network [OSTI]

; 6 Waste/Byproduct HydrogenWaste/By product Hydrogen Waste H2 sources include: Waste biomass: biogas Waste/Byproduct Hydrogen Waste/By product Hydrogen Fuel FlexibilityFuel Flexibility Biogas: generated

359

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 3. Revision 1  

SciTech Connect (OSTI)

This report consists of information related to the waste forms at the WIPP facility from the waste originators. Data for retrievably stored, projected and total wastes are given.

NONE

1995-02-01T23:59:59.000Z

360

Treatment of halogen-containing waste and other waste materials  

DOE Patents [OSTI]

A process is described for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes. 3 figs.

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

1997-03-18T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Treatment of halogen-containing waste and other waste materials  

DOE Patents [OSTI]

A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.

Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

1997-01-01T23:59:59.000Z

362

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216  

SciTech Connect (OSTI)

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

2013-07-01T23:59:59.000Z

363

Managing America's Defense Nuclear Waste | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste More Documents & Publications National Defense...

364

Experimental and Analytical Studies on Pyroelectric Waste Heat Energy Conversion  

E-Print Network [OSTI]

Waste heat Pyroelectric energy3 Pyroelectric Waste Heat Energy Harvesting Using Heat4 Pyroelectric Waste Heat Energy Harvesting Using Relaxor

Lee, Felix

2012-01-01T23:59:59.000Z

365

Self-irradiation damage of a curium-doped titanate ceramic containing sodium-rich high level nuclear waste  

SciTech Connect (OSTI)

This paper reports on the polyphase titanate ceramic containing sodium-rich simulated high-level nuclear waste doped with 0.69 wt% of {sup 244}Cm to accelerate long-term self-irradiation due to {alpha} decays. {alpha} autoradiography showed that {alpha} emissions were almost uniformly distributed throughout the curium-doped samples on a {gt} 20{mu}m scale although micropore surfaces and titanium oxide agglomerates were free of {alpha} emitting nuclides. The phase assemblage of the curium-doped titanate ceramic included freudenbergite and loveringite in addition to the more abundant oxide phases: hollandite, perovskite, and zirconolite. Accumulation of {alpha} decays was accompanied by a gradual decrease in density. The increment of density was {minus}1% after an equivalent age of 5000 yr. Leach tests showed a slight rend toward higher total release of curium with equivalent age. The release of soluble nonradioactive elements (e.g., Na, Cs, Sr, and Ca) in the oldest specimens (equivalent age, 2000 yr) varied from specimen to specimen but, on average, were higher than specimens that had suffered a lower radiation dose.

Miyazaki, T. (Second Dept. of Nuclear Business, Ibaraki Center, Chiyoda Maintenance Ltd., Asahi, Kashima, Ibaraki 314-14 (JP)); White, T.J. (Electron Microscope Centre, Univ. of Queensland, St. Lucia, Brisbane 4067 (AU)); Mitamura, H.; Matsumoto, S.; Nukaga, K.; Togashi, Y.; Sagawa, T.; Tashiro, S. (Dept. of Environmental Safety Research, Japan Atomic Energy Research Inst., Tokai, Naka, Ibaraki 319-11 (JP)); Levins, D.M. (Environmental Science Program, Australian Nuclear Science and Technology Organisation, Lucas Heights Research Lab., Lucas Heights, New South Wales (AU)); Kikuchi, A. (Dept. of Reactor Fuel Examination, Japan Atomic Energy Research Inst., Tokai, Naka, Ibaraki 319-11 (JP))

1990-11-01T23:59:59.000Z

366

Results of the radiological survey at the Sacandaga site Glenville, New York. Waste Management Research and Development Programs  

SciTech Connect (OSTI)

The Sacandaga site, located on Sacandaga Road, Glenville, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1951. Originally used for the study and development of radar during World War II, the facilities housed later operations involving physics studies and sodium technology development in support of breeder reactor design and other AEC programs. Though not in use since the original equipment was dismantled and removed in the early 1950s, portions of the 51-acre site are known to contain buried rubble from demolished structures used in former operations. At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a characterization of current radiological conditions over the site was performed between August and October 1989. The survey included the measurement of direct radiation levels (gamma, alpha, and beta-gamma) over all surfaces both inside and outside the building and tunnel, radionuclide analysis of systematic, biased, and auger hole soil samples, and analysis of sediments from underground structures. Gamma logging of auger holes was conducted and removable contamination levels inside the tunnel were determined. Samples of soil and structural materials from within and around an excavated concrete bunker were analyzed to determine concentrations of radionuclides and nonradioactive elemental beryllium.

Foley, R.D.; Cottrell, W.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

367

Nuclear waste management. Semiannual progress report, October 1983-March 1984  

SciTech Connect (OSTI)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.

McElroy, J.L.; Powell, J.A.

1984-06-01T23:59:59.000Z

368

Municipal Solid Waste:  

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

Methodology for Allocating Municipal Solid Waste Methodology for Allocating Municipal Solid Waste to Biogenic and Non-Biogenic Energy May 2007 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy of the Department of Energy or any other organization. Contact This report was prepared by staff of the Renewable Information Team, Coal, Nuclear, and Renewables Division, Office of Coal, Nuclear, Electric and Alternate Fuels.

369

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

370

Waste | OpenEI  

Open Energy Info (EERE)

Waste Waste Dataset Summary Description The Planning Database Project provides the UK Department of Energy and Climate Change (DECC) with regular data to track progress towards achieving EU targets for electricity generation from renewable energy (RE) sources. Extracts from the database are available each month. Information collected in the database includes: name, location and installed capacity of RE projects over 0.1MW; environmental designations; planning status; and construction status. Included here is the October 2010 Progress Datasheet, and an extract from December, 15, 2010 (i.e. Source UK Department of Energy and Climate Change (DECC) Date Released December 15th, 2010 (3 years ago) Date Updated Unknown Keywords biomass co-firing installed capacity

371

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

372

SRS - Programs - Liquid Waste Disposition  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

373

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

374

Method for processing aqueous wastes  

DOE Patents [OSTI]

A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

375

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

Broader source: Energy.gov (indexed) [DOE]

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

376

Regulatory decision-making under uncertainty: Are costs proportionate to benefits when restricting dangerous chemicals on European markets?  

Science Journals Connector (OSTI)

Abstract Since 2007 regulation 1907/2006/EC concerning the Registration, Evaluation, Authorization and Restriction of Chemicals (REACH) is in force in Europe to reduce the adverse effects of hazardous chemical substances on human health and the environment. Implementation of the regulation by the European Chemicals Agency (ECHA) is supported by a Socio-Economic Analysis (SEA) Committee, consisting of European experts who help prepare ECHA’s opinion on proposals for either restricting or authorizing dangerous substances. This paper presents the outcomes of the SEA underlying the first restriction proposals. Member states proposing a restriction have to show that it will reduce the risks to an acceptable level at a cost which is proportionate to the avoided risk. What is considered proportionate is not clearly defined in REACH. The opinion making process is characterized by many uncertainties: the expert group had no previous experiences to fall back on and limited information about the expected costs and benefits of the proposed restrictions. The study provides insight into expert opinions on environmental and health risks under uncertainty in the specific context of REACH. Particular attention is paid to the confidence experts place on the estimated socio-economic benefits of the avoided risks compared to the estimated compliance costs.

Roy Brouwer; Jonathan Cauchi; Julia Verhoeven

2014-01-01T23:59:59.000Z

377

Waste Growth Challenges Local Democracy. The Politics of Waste between Europe and the Mediterranean: a Focus on Italy  

E-Print Network [OSTI]

activities, such as waste burning versus waste dumping.and the Geographies of Waste Governance: A Burning Issue forEurope: • Burning oriented – Incineration (waste-to-energy)

Mengozzi, Alessandro

2010-01-01T23:59:59.000Z

378

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network [OSTI]

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

379

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network [OSTI]

/spills and subsequent clean up costs ($20,000) Sewage Sludge Volume Reduction 234,000 Radioactive Waste $910,000 $193,400 $716,600 60,000 gallons of radioactive STP liquid waste could have been disposed of through,000) Digital Imaging System Substitution 282 Hazardous Waste / Radioactive Waste / Industrial Waste $25,000 $25

380

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network [OSTI]

equipment. Savings are based on the cost of one PCB spill and clean-up event. Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission Reduction 0 Radioactive Emissions $0

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Hydration Aging of Nuclear Waste Glass  

Science Journals Connector (OSTI)

...of Nuclear Waste Glass 10...STEINDLER Chemical Engineering...60439 The aging of simulated nuclear waste glass by...nuclear waste forms can meet...simulated aging reac-tions...whether a waste formn can...pro-jected Nuclear Regulatory...STEINDLEt Chemical Engineering...Basisfor Waste Form Integrity...

J. K. BATES; L. J. JARDINE; M. J. STEINDLER

1982-10-01T23:59:59.000Z

382

Waste Management | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

July 27, 2011 July 27, 2011 End of Year 2010 SNF & HLW Inventories Map of the United States of America that shows the location of approximately 64,000 MTHM of Spent Nuclear Fuel (SNF) & 275 High-Level Radioactive Waste (HLW) Canisters. July 27, 2011 FY 2007 Total System Life Cycle Cost, Pub 2008 The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program presents the Office of Civilian Radioactive Waste Management's (OCRWM) May 2007 total system cost estimate for the disposal of the Nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TSLCC analysis provides a basis for assessing the adequacy of the Nuclear Waste Fund (NWF) Fee as required by Section 302 of the Nuclear Waste Policy Act of 1982 (NWPA), as amended.

383

Waste/By-Product Hydrogen  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

WASTE/BY-PRODUCT HYDROGEN WASTE/BY-PRODUCT HYDROGEN Ruth Cox DOE/DOD Workshop January 13, 2011 January 13, 2011 Fuel Cell and Hydrogen Energy Association The Fuel Cell and Hydrogen Energy Association FCHEA ƒ Trade Association for the industry ƒ Member driven - Market focused ƒ Developers, suppliers, customers, nonprofits, government Ad ƒ Advocacy ƒ Safety and standardization ƒ Education ƒ Strategic Alliances Fuel Cell and Hydrogen Energy Association O M b Our Members 5 W t /B d t H d Waste/By-product Hydrogen Overview Overview ƒ Growing populations, rising standards of living, and increased urbanization leads to a escalating volume of waste leads to a escalating volume of waste. ƒ Huge volumes of waste are collected in dumps, creating a major environmental issue. ƒ ƒ Wastewater treatment plants generate noxious gasses that are released in Wastewater treatment plants generate noxious gasses that are released in

384

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Carlsbad, New Mexico 8822 Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this document and all enclosures were prepared under our direction or supervision according to a system designed to assure that qualified personnel properly gather and evaluate the information submitted

385

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1  

SciTech Connect (OSTI)

This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

NONE

1995-02-01T23:59:59.000Z

386

Hydrothermal Processing of Wet Wastes  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Mill Waste, Plastic Bottles Aquatic Water Hyacinths, Kelp (Marine), Red Algae (Marine), Green Algae (Brackish), Green Algae (Marine), Green Algae (Fresh), Diatoms, Cyanobacteria...

387

Chernobyl’s waste site  

SciTech Connect (OSTI)

An analysis of the prospects for using the Chernobyl exclusion zone for development of a spent fuel store, waste disposal site and other nuclear facilities.

Schmieman, Eric A.; Paskevych, Sergiy; Sizov, Andrey; Batiy, Valeriy

2007-02-15T23:59:59.000Z

388

Process for preparing liquid wastes  

DOE Patents [OSTI]

A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

Oden, Laurance L. (Albany, OR); Turner, Paul C. (Albany, OR); O'Connor, William K. (Lebanon, OR); Hansen, Jeffrey S. (Corvallis, OR)

1997-01-01T23:59:59.000Z

389

Funds denied for nuclear waste  

Science Journals Connector (OSTI)

... curb on the amount of nuclear waste that can be stored in the state's West Valley .facility, which has been closed since 1972. ...

David Dickson

1979-05-24T23:59:59.000Z

390

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

7, 2014 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE May 7, 2014 Richland, WA Topics in this Meeting Summary Opening ......

391

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

June 9, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE MEETING June 9, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions...

392

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Permit (Permit), introduced the discussion of Permit units that relate to tanks. Liz said the Permit was last available for review in 1994. There have been revisions...

393

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

... 2 Review of Responses to HAB Advice 271 Leaking Tanks and HAB Advice 273 Openness and Transparency Related to Tank Waste Treatment...

394

Waste/By-Product Hydrogen  

Broader source: Energy.gov [DOE]

Presentation by Ruth Cox, Fuel Cell and Hydrogen Energy Association, at the DOE-DOD Waste-to-Energy using Fuel Cells Workshop held Jan. 13, 2011

395

Progress Update: TRU Waste Shipping  

SciTech Connect (OSTI)

A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

396

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

or statements that outline goals, objectives, and methods for source reduction and recycling of hazardous and mixed waste at the facility; 2. Employee training or incentive...

397

Reporting Fraud, Waste, and Abuse  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Notice reminds all DOE employees of their duty to report allegations of fraud, waste, and abuse to the Office of Inspector General. No cancellation.

2004-09-15T23:59:59.000Z

398

Nuclear waste could bury itself  

Science Journals Connector (OSTI)

... we can have strong scientific confidence in," says the chairman of Britain's Radioactive Waste Management Advisory Committee, Charles Curtis, a geochemist at the University of Manchester. ...

Tom Clarke

2003-08-13T23:59:59.000Z

399

Tank Waste Committee - Transcribed Flipcharts  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

TRU waste retrieval Provided the State of New Mexico concurs Determine not HLW (process knowledge) As long as meets all applicable requirements "evaluation" not...

400

Evaluation of the potential for significant ammonia releases from Hanford waste tanks  

SciTech Connect (OSTI)

Ammonia is ubiquitous as a component of the waste stored in the Hanford Site single-shell tanks (SSTs) and double-shell tanks (DSTs). Because ammonia is both flammable and toxic, concerns have been raised about the amount of ammonia stored in the tanks and the possible mechanisms by which it could be released from the waste into the head space inside the tanks as well as into the surrounding atmosphere. Ammonia is a safety issue for three reasons. As already mentioned, ammonia is a flammable gas and may contribute to a flammability hazard either directly, if it reaches a high enough concentration in the tank head space, or by contributing to the flammability of other flammable gases such as hydrogen (LANL 1994). Ammonia is also toxic and at relatively low concentrations presents a hazard to human health. The level at which ammonia is considered Immediately Dangerous to Life or Health (IDLH) is 300 ppm (WHC 1993, 1995). Ammonia concentrations at or above this level have been measured inside the head space in a number of SSTs. Finally, unlike hydrogen and nitrous oxide, ammonia is highly soluble in aqueous solutions, and large amounts of ammonia can be stored in the waste as dissolved gas. Because of its high solubility, ammonia behaves in a qualitatively different manner from hydrogen or other insoluble gases. A broader range of scenarios must be considered in modeling ammonia storage and release.

Palmer, B.J.; Anderson, C.M.; Chen, G.; Cuta, J.M.; Ferryman, T.A.; Terrones, G.

1996-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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.


401

SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING  

SciTech Connect (OSTI)

This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

2011-01-12T23:59:59.000Z

402

222-S radioactive liquid waste line replacement and 219-S secondary containment upgrade, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is proposing to: (1) replace the 222-S Laboratory (222-S) radioactive liquid waste drain lines to the 219-S Waste Handling Facility (219-S); (2) upgrade 219-S by replacing or upgrading the waste storage tanks and providing secondary containment and seismic restraints to the concrete cells which house the tanks; and (3) replace the transfer lines from 219-S to the 241-SY Tank Farm. This environmental assessment (EA) has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, the Council on Environmental Quality Regulations for Implementing the Procedural Provisions of NEPA (40 Code of Federal Regulations [CFR] 1500-1508), and the DOE Implementing Procedures for NEPA (10 CFR 1021). 222-S is used to perform analytical services on radioactive samples in support of the Tank Waste Remediation System and Hanford Site environmental restoration programs. Activities conducted at 222-S include decontamination of analytical processing and support equipment and disposal of nonarchived radioactive samples. These activities generate low-level liquid mixed waste. The liquid mixed waste is drained through pipelines in the 222-S service tunnels and underground concrete encasements, to two of three tanks in 219-S, where it is accumulated. 219-S is a treatment, storage, and/or disposal (TSD) unit, and is therefore required to meet Washington Administrative Code (WAC) 173-303, Dangerous Waste Regulations, and the associated requirements for secondary containment and leak detection. The service tunnels are periodically inspected by workers and decontaminated as necessary to maintain as low as reasonably achievable (ALARA) radiation levels. Although no contamination is reaching the environment from the service tunnels, the risk of worker exposure is present and could increase. 222-S is expected to remain in use for at least the next 30 years to serve the Hanford Site environmental cleanup mission.

NONE

1995-01-01T23:59:59.000Z

403

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

Broader source: Energy.gov (indexed) [DOE]

ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

404

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

Broader source: Energy.gov (indexed) [DOE]

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

405

Phase chemistry and radionuclide retention of high level radioactive waste tank sludges  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate groundwaters with radionuclides and RCRA metals. Experimentation on such sludges is both dangerous and prohibitively expensive so there is a great advantage to developing artificial sludges. The US DOE Environmental Management Science Program (EMSP) has funded a program to investigate the feasibility of developing such materials. The following text reports on the success of this program, and suggests that much of the radioisotope inventory left in a tank will not move out into the surrounding environment. Ultimately, such studies may play a significant role in developing safe and cost effective tank closure strategies.

KRUMHANSL,JAMES L.; BRADY,PATRICK V.; ZHANG,PENGCHU; ARTHUR,SARA E.; HUTCHERSON,SHEILA K.; LIU,J.; QIAN,M.; ANDERSON,HOWARD L.

2000-05-19T23:59:59.000Z

406

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

NONE

1996-04-01T23:59:59.000Z

407

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect (OSTI)

It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), and we coupled these two best-estimate accident analysis computer codes to model the ventilation system response to pressures and temperatures generated by the hydrogen and ammonia combustion.

Travis, J.R.; Fujita, R.K.; Spore, J.W.

1994-07-01T23:59:59.000Z

408

Tank Waste Remediation System Tank Waste Analysis Plan. FY 1995  

SciTech Connect (OSTI)

This documents lays the groundwork for preparing the implementing the TWRS tank waste analysis planning and reporting for Fiscal Year 1995. This Tank Waste Characterization Plan meets the requirements specified in the Hanford Federal Facility Agreement and Consent Order, better known as the Tri-Party Agreement.

Haller, C.S.; Dove, T.H.

1994-11-01T23:59:59.000Z

409

Radioactive waste processing apparatus  

DOE Patents [OSTI]

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

410

Nuclear Waste Policy Act | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Nuclear Waste Policy Act Nuclear Waste Policy Act Document on the Nuclear Waste Policy Act of 1982 An Act to provide for the development of repositories for the disposal of...

411

Available Options for Waste Disposal [and Discussion  

Science Journals Connector (OSTI)

...vitrified high-activity waste in properly selected deep...alternatives to present projects of waste disposal, but rather as...benefits will be different. Long-term storage of either spent fuel or vitrified waste, although not an alternative...

1986-01-01T23:59:59.000Z

412

Waste oil reduction: GKN  

SciTech Connect (OSTI)

This report details the steps required to establish a waste oil management program. Such a program can reduce operational costs, cut wastewater treatment costs and produce a better quality wastewater effluent through such means as: reducing the volume of oils used; segregating oils at the source of generation for recovery and reuse; and reducing the quality of oily wastewater generated. It discusses the metal-working fluid recovery options available for such a program, namely settling, filtration, hydrocyclone, and centrifugation. Included are source lists for vendors of oil skimmer equipment and coolant recovery systems.

Hunt, G.

1995-08-01T23:59:59.000Z

413

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility  

Broader source: Energy.gov (indexed) [DOE]

6 6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection Richland, Washington, 99352 07-DESIGN-046 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection under Contract DE-AC05-76RL01830 07-DESIGN-046 iii Summary The U.S. Department of Energy (DOE), Office of River Protection (ORP) and the DOE Office of Environmental and Radioactive Waste Management (EM), Office of Project Recovery have completed a

414

Microanalysis of colloids and suspended particles from nuclear waste glass alteration  

Science Journals Connector (OSTI)

Fully radioactive and non-radioactive Savannah River Laboratory (SRL) borosilicate glasses were reacted with water under static conditions at glass surface area to leachant volume (S/V) ratios of 340 m?1, 2000 m?1, and 20?000 m?1 for times varying from several days to several years at 90°C. A radioactive SRL 200 glass was also reacted under intermittent flow conditions at 90°C. Colloidal and suspended glass alteration particles present in the leachates of these tests were examined with analytical transmission electron microscopy (AEM). The major colloidal phase identified in all tests was partially crystalline dioctahedral smectite clay. At 20?000 m?1, the clay colloids flocculate and sediment, becoming attached to available surfaces when the ionic strength reached a value of about 0.3–0.5 mol·kg?1. Clay colloids remained stable in the solution for the duration of the experiment in tests conducted at S/V values of 2000 m?1 and 340 m?1. Calcite, dolomite, and transition metal oxide particles were more common in the intermittent flow tests but were also found in the static tests. Layered, Mn-bearing minerals, birnessite and asbolane, were found exclusively in the intermittent flow tests. Weeksite and a U-Ti phase were found exclusively in the static tests. Partially crystalline rare earth-bearing calcium phosphate colloids, structurally related to rhabdophane, were found in both types of tests. These particles exhibited a negative Ce anomaly. The affinity of phosphate for Pu was investigated through geochemical modeling. The results from this study and others were used to form a picture of colloidal development in the leachate from waste glass testing.

Edgar C Buck; John K Bates

1999-01-01T23:59:59.000Z

415

Clear and Present Danger  

Science Journals Connector (OSTI)

......Sony and Lush Cosmetics and that from Anonymous over the 2011 Christmas period where more than 50,000 credit numbers were compromised...users and customers. It is legislators who are now acting, in light of such recent events, to deter hackers and prevent hacks......

Charlotte Walker-Osborn; Farhan Khalid

2012-01-01T23:59:59.000Z

416

Starch collars dangerous pests  

Science Journals Connector (OSTI)

... effective needs to be looked at," says Kabir Cham, a member of the World Health Organization's Roll Back Malaria programme, which works to replace DDT with safer insecticides. ...

Corie Lok

2001-05-18T23:59:59.000Z

417

A dangerous precedent  

Science Journals Connector (OSTI)

... groups joined forces with two scientists to file a lawsuit against the US Department of Health and Human Services and the National Institutes of ... and Human Services and the National Institutes of Health (NIH). The lawsuit charged that the Obama administration's embryonic stem-cell policy ...

2010-07-07T23:59:59.000Z

418

Little danger from radon  

Science Journals Connector (OSTI)

... the potential alpha energy in air from any combination of the short-lived daughters of radon. 1 WL = 1.3 ? 10" MeV nT3). A recent survey ( ... Biol 23, 696-711; 1978) estimated that the average population exposure rate domestically to radon daughters for Great Britain is about 0.15 WLM per year.

K. D. CLIFF; B. L. DAVIES; J. A. REISSLAND

1979-05-03T23:59:59.000Z

419

Hazardous Wastes Management (Alabama) | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Hazardous Wastes Management (Alabama) Hazardous Wastes Management (Alabama) Hazardous Wastes Management (Alabama) < Back Eligibility Commercial Construction Developer Industrial Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations Safety and Operational Guidelines This legislation gives regulatory authority to the Department of Environmental Management to monitor commercial sites for hazardous wastes; fees on waste received at such sites; hearings and investigations. The legislation also states responsibilities of generators and transporters of hazardous waste as well as responsibilities of hazardous waste storage and treatment facility and hazardous waste disposal site operators. There

420

Independent Oversight Assessment, Salt Waste Processing Facility...  

Broader source: Energy.gov (indexed) [DOE]

Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department of Energy...

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

422

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

423

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

424

Independent Oversight Activity Report, Hanford Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

and Tank Farm - January 2014 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant and Tank Farm - January 2014 January 2014 Hanford Waste...

425

Independent Oversight Activity Report, Hanford Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

July 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - July 2013 July 2013 Operational Awareness of Waste Treatment and Immobilization...

426

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Waste Treatment and Immobilization Plant - November 2011 November 2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

427

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Review, Waste Treatment and Immobilization Plant - March 2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S....

428

Oversight Reports - Waste Isolation Pilot Plant | Department...  

Broader source: Energy.gov (indexed) [DOE]

2011 Orientation Visit to the Waste Isolation Pilot Plant HIAR-WIPP-2011-09-07 November 26, 2007 Independent Oversight Inspection, Waste Isolation Pilot Plant - December 2007...

429

Environmental Management Waste Management Facility (EMWMF) at...  

Office of Environmental Management (EM)

Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Full Document and Summary Versions...

430

Development of Thermoelectric Technology for Automotive Waste...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Thermoelectric Technology for Automotive Waste Heat Recovery Development of Thermoelectric Technology for Automotive Waste Heat Recovery Overview and status of project to develop...

431

Development of Thermoelectric Technology for Automotive Waste...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Thermoelectric Technology for Automotive Waste Heat Recovery Development of Thermoelectric Technology for Automotive Waste Heat Recovery Presentation from the U.S. DOE Office of...

432

WIPP Receives Waste Characterized With Mobile System  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

For Immediate Release WIPP Receives Waste Characterized With Mobile System CARLSBAD, N.M., April 12, 2002 - The first shipment of transuranic waste characterized by the Central...

433

Independent Oversight Activity Report, Hanford Waste Treatment...  

Office of Environmental Management (EM)

of River Protection review of the High Level Waste Facility heating, ventilation, and air conditioning systems. Independent Oversight Activity Report, Hanford Waste Treatment...

434

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

the melter handling system (LMH), the melter equipment support handling system (LSH), the radioactive solid waste handling system (RWH), and the radioactive liquid waste disposal...

435

Missouri Hazardous Waste Management Law (Missouri)  

Broader source: Energy.gov [DOE]

The Hazardous Waste Program, administered by the Hazardous Waste Management Commission in the Department of Natural Resources, regulates the processing, transportation, and disposal of hazardous...

436

Civilian Radioactive Waste Management System Requirements Document...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level...

437

Nuclear waste storage bill passes Congress  

Science Journals Connector (OSTI)

Nuclear waste storage bill passes Congress ... The law sets up provisions to evaluate ways to store spent nuclear fuel and wastes. ...

1983-01-03T23:59:59.000Z

438

Independent Oversight Activity Report, Hanford Waste Treatment...  

Energy Savers [EERE]

October 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - October 2013 October 2013 Observation of Waste Treatment and Immobilization...

439

Sandia National Laboratories: Defense Waste Management Programs  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Programs provides scientific analyses and programmatic advice to the U.S. Department of Energy in support of defense waste management challenges. Defense waste encompasses...

440

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers [EERE]

Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project -...

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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

Voluntary Protection Program Onsite Review, Transuranic Waste...  

Energy Savers [EERE]

Transuranic Waste Processing Center - September 2012 Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center - September 2012 September 2012 Evaluation to...

442

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers [EERE]

Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project...

443

Sandia National Laboratories: radiation waste cleanup  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

waste cleanup ECIS and UOP (a Honewell Company): CSTs Clean Radioactive Waste in Fukushima and Worldwide On February 14, 2013, in Energy, Materials Science, Nuclear Energy,...

444

Independent Oversight Review, Waste Treatment and Immobilization...  

Energy Savers [EERE]

January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant...

445

Aluminoborosilicate Waste Glass Dissolution under Alkaline Conditions...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Aluminoborosilicate Waste Glass Dissolution under Alkaline Conditions at 40°C: Implications for a Chemical Affinity-Based Aluminoborosilicate Waste Glass Dissolution under...

446

Waste Management Programmatic Environmental Impact Statement...  

Office of Environmental Management (EM)

Waste Management Programmatic Environmental Impact Statement (WM PEIS) Reports and Records of Decision Waste Management Programmatic Environmental Impact Statement (WM PEIS)...

447

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

448

Independent Oversight Assessment, Waste Treatment and Immobilization...  

Office of Environmental Management (EM)

Waste Treatment and Immobilization Plant - January 2012 Independent Oversight Assessment, Waste Treatment and Immobilization Plant - January 2012 January 2012 Assessment of the...

449

Municipal Solid Waste Resources and Technologies  

Broader source: Energy.gov [DOE]

This page provides a brief overview of municipal solid waste energy resources and technologies supplemented by specific information to apply waste to energy within the Federal sector.

450

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Environmental Management (EM)

Waste Treatment and Immobilization Plant Project - October 2010 October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant...

451

The e-waste impact  

Science Journals Connector (OSTI)

The e-services have gained a wide range of attention and became an indispensable part of the majority of people and nations' life and living. New technology is constantly emerging making that old working gadget no longer desirable. On the other hand, ... Keywords: WEEE, e-waste, environment and health hazards, high tech waste, recycle, treatment

Mansour Jaragh; Jenan Boushahri

2009-11-01T23:59:59.000Z

452

The reduction of packaging waste  

SciTech Connect (OSTI)

Nationwide, packaging waste comprises approximately one-third of the waste disposed in sanitary landfills. the US Department of Energy (DOE) generated close to 90,000 metric tons of sanitary waste. With roughly one-third of that being packaging waste, approximately 30,000 metric tons are generated per year. The purpose of the Reduction of Packaging Waste project was to investigate opportunities to reduce this packaging waste through source reduction and recycling. The project was divided into three areas: procurement, onsite packaging and distribution, and recycling. Waste minimization opportunities were identified and investigated within each area, several of which were chosen for further study and small-scale testing at the Hanford Site. Test results, were compiled into five ``how-to`` recipes for implementation at other sites. The subject of the recipes are as follows: (1) Vendor Participation Program; (2) Reusable Containers System; (3) Shrink-wrap System -- Plastic and Corrugated Cardboard Waste Reduction; (4) Cardboard Recycling ; and (5) Wood Recycling.

Raney, E.A.; Hogan, J.J.; McCollom, M.L.; Meyer, R.J.

1994-04-01T23:59:59.000Z

453

Reporting Fraud, Waste, and Abuse  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To notify all Department of Energy (DOE) employees, including National Nuclear Security Administration (NNSA) employees, of their duty to report allegations of fraud, waste, and abuse to the appropriate authorities, including the DOE Office of Inspector General (OIG). Cancels: DOE N 221.12, Reporting Fraud, Waste, and Abuse, dated 10-19-06

2006-12-15T23:59:59.000Z

454

Solving the Nuclear Waste Problem  

Science Journals Connector (OSTI)

Solving the Nuclear Waste Problem ... Of the many problems that beset the nuclear power industry, none has proved as perplexing as taking out the trash. ... Nuclear waste will remain a potential threat to man and the environment for as long as 10,000 years. ...

1988-09-12T23:59:59.000Z

455

Generating Steam by Waste Incineration  

E-Print Network [OSTI]

Combustible waste is a significant source of steam at the new John Deere Tractor Works assembly plant in Waterloo, Iowa. The incinerators, each rated to consume two tons of solid waste per hour, are expected to provide up to 100 percent of the full...

Williams, D. R.; Darrow, L. A.

1981-01-01T23:59:59.000Z

456

Nevada Waste Leaves Idaho Facility  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Media Contacts: Media Contacts: Danielle Miller, 208-526-5709 Brad Bugger, 208-526-0833 For Immediate Release: Date: March 02, 2010 Nevada Waste Leaves Idaho Facility (Note: This is a reissue of a press release originally sent last week to ensure all intended recipients receive a copy after technical glitch may have kept it from reaching some of them) It may have looked like just another shipment of transuranic radioactive waste leaving Idaho, but the shipment heading south on U.S. Interstate 15 the afternoon of January 26 actually contained waste from another DOE site in Nevada. The shipment demonstrated the capacity of the U.S. Department of Energy�s Advanced Mixed Waste Treatment Project to be a hub where the Department�s transuranic radioactive waste can be safely and compliantly

457

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

458

WIMS - Waste Information Management System  

Office of Environmental Management (EM)

Welcome To WIMS Welcome To WIMS Waste Information Management System WIMS new web address: http://www.emwims.org WIMS is developed to provide DOE Headquarters and site waste managers with the tools necessary to easily visualize, understand, and manage the vast volumes, categories, and problems of forecasted waste streams. WIMS meets this need by providing a user-friendly online system to gather, organize, and present waste forecast data from DOE sites. This system provides a method for identification of waste forecast volumes, material classes, disposition pathways, and potential choke points and barriers to final disposition. Disclaimer: Disposition facility information presented is for planning purposes only and does not represent DOE's decisions or commitments. Any selection of disposition facility will be made after technical, economic, and policy considerations.

459

Optimizing High Level Waste Disposal  

SciTech Connect (OSTI)

If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being evaluated at Idaho National Laboratory and the facilities we’ve designed to evaluate options and support optimization.

Dirk Gombert

2005-09-01T23:59:59.000Z

460

Process system evaluation-consolidated letters. Volume 1. Alternatives for the off-gas treatment system for the low-level waste vitrification process  

SciTech Connect (OSTI)

This report provides an evaluation of alternatives for treating off-gas from the low-level waste (LLW) melter. The study used expertise obtained from the commercial nonradioactive off-gas treatment industry. It was assumed that contact maintenance is possible, although the subsequent risk to maintenance personnel was qualitatively considered in selecting equipment. Some adaptations to the alternatives described may be required, depending on the extent of contact maintenance that can be achieved. This evaluation identified key issues for the off-gas system design. To provide background information, technology reviews were assembled for various classifications of off-gas treatment equipment, including off-gas cooling, particulate control, acid gas control, mist elimination, NO{sub x} reduction, and SO{sub 2} removal. An order-of-magnitude cost estimate for one of the off-gas systems considered is provided using both the off-gas characteristics associated with the Joule-heated and combustion-fired melters. The key issues identified and a description of the preferred off-gas system options are provided below. Five candidate treatment systems were evaluated. All of the systems are appropriate for the different melting/feed preparations currently being considered. The lowest technical risk is achieved using option 1, which is similar to designs for high-level waste (HLW) vitrification in the Hanford Waste Vitrification Project (HWVP) and the West Valley. Demonstration Project. Option 1 uses a film cooler, submerged bed scrubber (SBS), and high-efficiency mist eliminator (HEME) prior to NO{sub x} reduction and high-efficiency particulate air (HEPA) filtration. However, several advantages were identified for option 2, which uses high-temperature filtration. Based on the evaluation, option 2 was identified as the preferred alternative. The characteristics of this option are described below.

Peurrung, L.M.; Deforest, T.J; Richards, J.R.

1996-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nonradioactive dangerous waste" 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.


461

Acceptability of Bettis Laboratories waste shipment to WHC solid waste  

SciTech Connect (OSTI)

The purpose of this document is to evaluate a potential discrepancy between the Solid Waste Management (SWM) Criticality Prevention Specifications and a proposed waste receipt from Bettis Laboratories. This analysis resolves an apparent discrepancy between two different requirements of the Central Waste Complex and 200 Area Low-Level Burial Grounds Criticality Prevention Specifications (CPS-SW-149-00002 and CPS-SW-149-00003 respectively). The analysis is being performed to enable Solid Waste Management to accept a specific package from Bettis Laboratories. This package meets the requirements of section 2.1.1 in that the total fissile content of the drum is less than 200g and the waste occupies greater than 20% of the container volume. The package may not appear, however, to meet the requirements of section 2.1.5 for maximum enrichment of uranium bearing waste, as will be described below. Based on this analysis for this specific package, the waste is shown to be critically safe under all conditions for which the 55-gallon drums (17C, 17H, or UN1A2) specification applies. This package can be accepted under the 55-gallon drum limitations on fissile quantity. No change to the CPS is required.

McDonald, K.M.

1995-04-20T23:59:59.000Z

462

Los Alamos exceeds waste shipping goal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

463

Los Alamos exceeds waste shipping goal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

464

Waste Isolation Pilot Plant | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is contaminated with small amounts of plutonium and other TRU radioactive elements. Over the next 35 years, WIPP is expected to receive approximately 175,000 cubic meters of waste from various DOE sites. Enforcement September 8, 2006 Enforcement Letter, Washington TRU Solutions - September 8, 2006

465

Technological enhancements in TRU waste management.  

SciTech Connect (OSTI)

On March 26, 1999, the Waste Isolation Pilot Plant (WIPP) received its first shipment of transuranic (TRU) waste. On November 26, 1999, the Hazardous Waste Facility Permit (HWFP) to receive mixed TRU waste at WIPP became effective. Having achieved these two milestones, facilitating and supporting the characterization, transportation, and disposal of TRU waste became the major challenges for the National TRU Waste Program. After the WIPP began receiving waste, it was evident that, at the rate at which TRU waste was being shipped to and received at WIPP, the facility was not being used to its full potential, nor would it be unless improvements to the TRU waste management system were made. This paper describes some of the efforts to optimize (to make as functional as possible) characterization, transportation, and disposal of TRU waste; some of the technological enhancements necessary to achieve an optimized national transuranic waste system (1); and the interplay between regulatory change and technology development

Elkins, N. Z. (Ned Z.); Moody, D. C. (David C.)

2002-01-01T23:59:59.000Z

466

Tank Waste Corporate Board | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Tank Waste Corporate Board Tank Waste Corporate Board Tank Waste Corporate Board The Tank Waste Corporate Board is a chartered group of senior DOE, contractor, and laboratory managers and staff that meets approximately semi-annually to formulate and coordinate implementation of an effective and efficient national Tank Waste program. August 1, 2012 Tank Waste Corporate Board Meeting 08/01/12 The following documents are associated with the Tank Waste Corporate Board Meeting held on August 1st, 2012. November 18, 2010 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. July 29, 2009 Tank Waste Corporate Board Meeting 07/29/09 The following documents are associated with the Tank Waste Corporate Board

467

Bacteria eats radioactive waste  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Bacteria eats radioactive waste Bacteria eats radioactive waste Name: deenaharper Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: In my studies, I have found that everything in this world is balanced. When something dies it is converted into life. Is there anything out there that could convert radioactive material into a harmless substance? Some sort of bacteria that consumes radiation? Replies: The reason why radiation is so harmful is that is produces free radicals in living tissue, that is, it de-stabilizes molecules by tearing off electrons due to intense energies. These free radicals start a chain reaction of destruction, de-stabilizing neighboring molecules. If this continues unchecked, cells die, genetic material are mutated, and tissue aging accelerates. It is somewhat like being burned. Fire oxidizes by a similar free radical reaction. (Hence the term "sun burn.") The natural defenses against free radical reactions in biological systems are antioxidants, which are enzymes, nutrients, and other chemicals, which quench free radical reactions. Without them, life would very quickly cease. To my knowledge, no microorganism has an antioxidant capacity great enough to withstand even minimal exposure to any type of radiation. Microorganisms are actually very susceptible to radiation, which is why heat and gamma irradiation are used to sterilize food, instruments, etc. However, you raise an interesting possibility in that perhaps one can be genetically engineered to have super- antioxidant capacity, but that may be beyond current technology. Plus, if any got loose, given the exponential rate of reproduction, they may become an uncontrollable health hazard, as it would be very difficult to destroy them!

468

An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects  

SciTech Connect (OSTI)

This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates.

Sexton, R.A.

1993-03-01T23:59:59.000Z

469

Tank Waste Disposal Program redefinition  

SciTech Connect (OSTI)

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

470

TRU waste-sampling program  

SciTech Connect (OSTI)

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of /sup 238/Pu- and /sup 239/Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with /sup 239/Pu-contaminated waste, but three 8-month-old drums of /sup 238/Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs.

Warren, J.L.; Zerwekh, A.

1985-08-01T23:59:59.000Z

471

Waste tire recycling by pyrolysis  

SciTech Connect (OSTI)

This project examines the City of New Orleans' waste tire problem. Louisiana State law, as of January 1, 1991, prohibits the knowing disposal of whole waste tires in landfills. Presently, the numerous waste tire stockpiles in New Orleans range in size from tens to hundreds of tires. New Orleans' waste tire problem will continue to increase until legal disposal facilities are made accessible and a waste tire tracking and regulatory system with enforcement provisions is in place. Tires purchased outside of the city of New Orleans may be discarded within the city's limits; therefore, as a practical matter this study analyzes the impact stemming from the entire New Orleans metropolitan area. Pyrolysis mass recovery (PMR), a tire reclamation process which produces gas, oil, carbon black and steel, is the primary focus of this report. The technical, legal and environmental aspects of various alternative technologies are examined. The feasibility of locating a hypothetical PMR operation within the city of New Orleans is analyzed based on the current economic, regulatory, and environmental climate in Louisiana. A thorough analysis of active, abandoned, and proposed Pyrolysis operations (both national and international) was conducted as part of this project. Siting a PMR plant in New Orleans at the present time is technically feasible and could solve the city's waste tire problem. Pending state legislation could improve the city's ability to guarantee a long term supply of waste tires to any large scale tire reclamation or recycling operation, but the local market for PMR end products is undefined.

Not Available

1992-10-01T23:59:59.000Z

472

LLNL Waste Minimization Program Plan  

SciTech Connect (OSTI)

This document is the February 14, 1990 version of the LLNL Waste Minimization Program Plan (WMPP). The Waste Minimization Policy field has undergone continuous changes since its formal inception in the 1984 HSWA legislation. The first LLNL WMPP, Revision A, is dated March 1985. A series of informal revision were made on approximately a semi-annual basis. This Revision 2 is the third formal issuance of the WMPP document. EPA has issued a proposed new policy statement on source reduction and recycling. This policy reflects a preventative strategy to reduce or eliminate the generation of environmentally-harmful pollutants which may be released to the air, land surface, water, or ground water. In accordance with this new policy new guidance to hazardous waste generators on the elements of a Waste Minimization Program was issued. In response to these policies, DOE has revised and issued implementation guidance for DOE Order 5400.1, Waste Minimization Plan and Waste Reduction reporting of DOE Hazardous, Radioactive, and Radioactive Mixed Wastes, final draft January 1990. This WMPP is formatted to meet the current DOE guidance outlines. The current WMPP will be revised to reflect all of these proposed changes when guidelines are established. Updates, changes and revisions to the overall LLNL WMPP will be made as appropriate to reflect ever-changing regulatory requirements. 3 figs., 4 tabs.

Not Available

1990-02-14T23:59:59.000Z

473

Development of a Performance and Processing Property Acceptance Region for Cementitious Low-Level Waste Forms at Savannah River Site - 13174  

SciTech Connect (OSTI)

The Saltstone Production and Disposal Facilities (SPF and SDF) at the Savannah River Site (SRS) have been treating decontaminated salt solution, a low-level aqueous waste stream (LLW) since facility commissioning in 1990. In 2012, the Saltstone Facilities implemented a new Performance Assessment (PA) that incorporates an alternate design for the disposal facility to ensure that the performance objectives of DOE Order 435.1 and the National Defense Authorization Act (NDAA) of Fiscal Year 2005 Section 3116 are met. The PA performs long term modeling of the waste form, disposal facility, and disposal site hydrogeology to determine the transport history of radionuclides disposed in the LLW. Saltstone has been successfully used to dispose of LLW in a grout waste form for 15 years. Numerous waste form property assumptions directly impact the fate and transport modeling performed in the PA. The extent of process variability and consequence on performance properties are critical to meeting the assumptions of the PA. The SPF has ensured performance property acceptability by way of implementing control strategies that ensure the process operates within the analyzed limits of variability, but efforts continue to improve the understanding of facility performance in relation to the PA analysis. A similar understanding of the impact of variability on processing parameters is important from the standpoint of the operability of the production facility. The fresh grout slurry properties (particularly slurry rheology and the rate of hydration and structure formation) of the waste form directly impact the pressure and flow rates that can be reliably processed. It is thus equally important to quantify the impact of variability on processing parameters to ensure that the design basis assumptions for the production facility are maintained. Savannah River Remediation (SRR) has been pursuing a process that will ultimately establish a property acceptance region (PAR) to incorporate elements important to both processability and long-term performance properties. This process involves characterization of both emplaced product samples from the disposal facility and laboratory-simulated samples to demonstrate the effectiveness of the lab simulation. With that basis confirmed, a comprehensive variability study using non-radioactive simulants will define the acceptable PAR, or 'operating window' for Saltstone production and disposal. This same process will be used in the future to evaluate new waste streams for disposal or changes to the existing process flowsheet. (authors)

Staub, Aaron V. [Savannah River Remediation, Aiken, SC 29808 (United States)] [Savannah River Remediation, Aiken, SC 29808 (United States); Reigel, Marissa M. [Savannah River National Lab, Aiken, SC 29808 (United States)] [Savannah River National Lab, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

474

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

475

RCRA Assessment Plan for Single-Shell Tank Waste Management Area S-SX at the Hanford Site  

SciTech Connect (OSTI)

A groundwater quality assessment plan was prepared for waste management area S-SX at the Hanford Site. Groundwater monitoring is conducted at this facility in accordance with Title 40, Code of Federal Regulation (CFR) Part 265, Subpart F [and by reference of Washington Administrative Code (WAC) 173-303-400(3)]. The facility was placed in assessment groundwater monitoring program status after elevated waste constituents and indicator parameter measurements