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Note: This page contains sample records for the topic "waste storage building" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

2401-W Waste storage building closure plan  

SciTech Connect

This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

LUKE, S.M.

1999-07-15T23:59:59.000Z

2

EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings  

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

0: Construction of Mixed Waste Storage RCRA Facilities, 0: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee SUMMARY This EA evaluates the environmental impacts of a proposal to construct and operate two mixed (both radioactive and hazardous) waste storage facilities (Buildings 7668 and 7669) in accordance with Resource Conservation and Recovery Act requirements. Site preparation and construction activities would take place at the U.S. Department of Energy's Oak Ridge National Laboratory in Oak Ridge, Tennessee. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 16, 1994 EA-0820: Finding of No Significant Impact

3

Evaluation of existing Hanford buildings for the storage of solid wastes  

SciTech Connect

Existing storage space at the Hanford Site for solid low-level mixed waste (LLMW) will be filled up by 1997. Westinghouse Hanford Company (WHC) has initiated the project funding cycle for additional storage space to assure that new facilities are available when needed. In the course of considering the funding request, the US Department of Energy (DOE) has asked WHC to identify and review any existing Hanford Site facilities that could be modified and used as an alternative to constructing the proposed W-112 Project. This report documents the results of that review. In summary, no buildings exist at the Hanford Site that can be utilized for storage of solid LLMW on a cost-effective basis when compared to new construction. The nearest approach to an economically sensible conversion would involve upgrade of 100,000 ft{sup 2} of space in the 2101-M Building in the 200 East Area. Here, modified storage space is estimated to cost about $106 per ft{sup 2} while new construction will cost about $50 per ft{sup 2}. Construction costs for the waste storage portion of the W-112 Project are comparable with W-016 Project actual costs, with escalation considered. Details of the cost evaluation for this building and for other selected candidate facilities are presented in this report. All comparisons presented address the potential decontamination and decommissioning (D&D) cost avoidances realized by using existing facilities.

Carlson, M.C.; Hodgson, R.D.; Sabin, J.C.

1993-05-01T23:59:59.000Z

4

FOREST CENTRE STORAGE BUILDING  

E-Print Network (OSTI)

FOREST CENTRE STORAGE BUILDING 3 4 5 6 7 8 UniversityDr. 2 1 G r e n f e l l D r i v e MULTI BUILDING STORAGE BUILDING LIBRARY & COMPUTING FINE ARTS FOREST CENTRE ARTS &SCIENCE BUILDING ARTS &SCIENCE BUILDING A&S BUILDING EXTENSIO N P7 P5.1 P5 P2 P3.1 P3.2 P6 P8 P4 P2 P2 P4 P8 P2.4 PARKING MAP GRENFELL

deYoung, Brad

5

Warehouse and Storage Buildings  

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

Warehouse and Storage Warehouse and Storage Characteristics by Activity... Warehouse and Storage Warehouse and storage buildings are those used to store goods, manufactured products, merchandise, raw materials, or personal belongings. Basic Characteristics [ See also: Equipment | Activity Subcategories | Energy Use ] Warehouse and Storage Buildings... While the idea of a warehouse may bring to mind a large building, in reality most warehouses were relatively small. Forty-four percent were between 1,001 and 5,000 square feet, and seventy percent were less than 10,000 square feet. Many warehouses were newer buildings. Twenty-five percent were built in the 1990s and almost fifty percent were constructed since 1980. Tables: Buildings and Size Data by Basic Characteristics Establishment, Employment, and Age Data by Characteristics

6

Radioactive waste storage issues  

SciTech Connect

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

7

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network (OSTI)

The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the ...

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

8

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology  

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

46: Radioactive Waste Storage at Rocky Flats Environmental 46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste storage facilities in order to increase storage capacity for low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 9, 1996 EA-1146: Finding of No Significant Impact Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

9

Preparing Class B and C Waste for Long Term Storage  

SciTech Connect

Commercial Nuclear Generating Stations outside of the Atlantic Compact will lose access to the Barnwell Disposal Facility in July of 2008. Many generators have constructed Interim On-Site Storage Buildings (IOSB) in which to store class B and C waste in the future as other permanent disposal options are developed. Until such time it is important for these generators to ensure class B and C waste generation is minimized and waste generated is packaged to facilitate long term storage. (authors)

Snyder, M.W. [Sacramento Municipal Utility District - Rancho Seco (United States)

2008-07-01T23:59:59.000Z

10

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

11

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

12

Electric Storage in California's Commercial Buildings  

E-Print Network (OSTI)

Distributed photovoltaic generation and energy storageenergy management in buildings and microgrids with e.g. installed Photovoltaic (energy storage, TS – thermal storage, FB – Flow Battery, AC – Absorption Chiller, ST – solar thermal system, PV – photovoltaic.

Stadler, Michael

2014-01-01T23:59:59.000Z

13

Thermal Energy Storage for Cooling of Commercial Buildings  

E-Print Network (OSTI)

of Commercial Building Thermal Energy _Storage in ASEANGas Electric Company, "Thermal Energy Storage for Cooling,"LBL--25393 DE91 ,THERMAL ENERGY STORAGE FOR COOLING OF

Akbari, H.

2010-01-01T23:59:59.000Z

14

Thermal Energy Storage for Cooling of Commercial Buildings  

E-Print Network (OSTI)

For the ice storage system, during direct cooling, thethe building cooling load. In dynamic systems, ice is formedcooling/demand-limited storage / electric load management / full storage / ice

Akbari, H.

2010-01-01T23:59:59.000Z

15

Site Visit Report, Hanford Waste Encapsulation Storage Facility...  

Energy Savers (EERE)

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 January 2011 Hanford...

16

Status Update: Extended Storage and Transportation Waste Confidence...  

Office of Environmental Management (EM)

Status Update: Extended Storage and Transportation Waste Confidence Status Update: Extended Storage and Transportation Waste Confidence Presentation made by David W. Pstrak for the...

17

Long-term nuclear waste storage urged  

Science Journals Connector (OSTI)

Long-term nuclear waste storage urged ... Nuclear waste should be stored for at least 100 years before being disposed of permanently, says a multinational committee from the International Council of Scientific Unions (ICSU). ... The recommendations of the ICSU Committee on Terrestrial Disposal of Nuclear Wastes, headed by geochemistry professor William S. Fyfe of the University of Western Ontario, were published in ... ...

1984-08-27T23:59:59.000Z

18

Permitting plan for the high-level waste interim storage  

SciTech Connect

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

Deffenbaugh, M.L.

1997-04-23T23:59:59.000Z

19

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities  

E-Print Network (OSTI)

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities Ron Fulbright Inspector (SWAMI) is a prototype mobile robot designed to perform autonomous inspection of nuclear waste user interface building tool called UIM/X. Introduction Safe disposal of nuclear waste is a difficult

Stephens, Larry M.

20

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

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

Note: This page contains sample records for the topic "waste storage building" 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

Canister storage building trade study. Final report  

SciTech Connect

This study was performed to evaluate the impact of several technical issues related to the usage of the Canister Storage Building (CSB) to safely stage and store N-Reactor spent fuel currently located at K-Basin 100KW and 100KE. Each technical issue formed the basis for an individual trade study used to develop the ROM cost and schedule estimates. The study used concept 2D from the Fluor prepared ``Staging and Storage Facility (SSF) Feasibility Report`` as the basis for development of the individual trade studies.

Swenson, C.E. [Westinghouse Hanford Co., Richland, WA (United States)

1995-05-01T23:59:59.000Z

22

Building 251 Radioactive Waste Characterization by Process Knowledge  

SciTech Connect

Building 251 is the Lawrence Livermore National Laboratory Heavy Elements Facility. Operations that involved heavy elements with uncontained radioisotopes including transuranic elements took place inside of glove boxes and fume hoods. These operations included process and solution chemistry, dissolutions, titrations, centrifuging, etc., and isotope separation. Operations with radioactive material which presently take place outside of glove boxes include storage, assaying, packing and unpacking and inventory verification. Wastes generated inside glove boxes will generally be considered TRU or Greater Than Class C (GTCC). Wastes generated in the RMA, outside glove boxes, is presumed to be low level waste. This process knowledge quantification method may be applied to waste generated anywhere within or around B251. The method is suitable only for quantification of waste which measures below the MDA of the Blue Alpha meter (i.e. only material which measures as Non-Detect with the blue alpha is to be characterized by this method).

Dominick, J L

2002-05-29T23:59:59.000Z

23

States want say in nuclear waste storage  

Science Journals Connector (OSTI)

The states have put Congress and the executive branch on notice that they want a very active role in deciding where and how the nation's nuclear wastes will be stored. ... The 19-member State Planning Council on Radioactive Waste Management, appointed by President Carter in February 1980, in its interim report says that it is seeking a middle ground between giving states or Indian tribes a veto over the siting of long-term nuclear waste storage facilities and pre-emptive imposition of federal will. ...

1981-04-06T23:59:59.000Z

24

Hazardous Waste/Mixed Waste Treatment Building throughput study  

SciTech Connect

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

25

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)  

SciTech Connect

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Burgard, K.C.

1998-04-09T23:59:59.000Z

26

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

SciTech Connect

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

27

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

28

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

29

Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage Vishal Kher and Yongdae Kim  

E-Print Network (OSTI)

Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage Vishal Kher and Yongdae. While storage outsourcing is cost-effective, many compa- nies are hesitating to outsource their storage due to security concerns. The success of storage outsourcing is highly de- pendent on how well

Kim, Dae-Shik

30

Report of Survey of Oak Ridge Building 3597 Hot Storage Garden | Department  

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

Building 3597 Hot Storage Garden Building 3597 Hot Storage Garden Report of Survey of Oak Ridge Building 3597 Hot Storage Garden The purpose of this document is to report the results of a survey conducted at the Hot Storage Garden facility (identified as "Building" 3597) on the Y-12 Plant property at the Oak Ridge Site. The survey was conducted during the week of 11/15/99. The primary purpose of the survey is to identify facility conditions and to define the characterization, stabilization, and material/waste/equipment removal (if any) requirements that need to be met to transfer responsibility for the facility from the Office of Science (SC) to the Office of Environmental Management (EM). Additionally, estimated post stabilization surveillance and maintenance (S&M) activities and costs are

31

Report of Survey of Oak Ridge Building 3597 Hot Storage Garden | Department  

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

Building 3597 Hot Storage Garden Building 3597 Hot Storage Garden Report of Survey of Oak Ridge Building 3597 Hot Storage Garden The purpose of this document is to report the results of a survey conducted at the Hot Storage Garden facility (identified as "Building" 3597) on the Y-12 Plant property at the Oak Ridge Site. The survey was conducted during the week of 11/15/99. The primary purpose of the survey is to identify facility conditions and to define the characterization, stabilization, and material/waste/equipment removal (if any) requirements that need to be met to transfer responsibility for the facility from the Office of Science (SC) to the Office of Environmental Management (EM). Additionally, estimated post stabilization surveillance and maintenance (S&M) activities and costs are

32

Hydrogen storage systems from waste Mg alloys  

Science Journals Connector (OSTI)

Abstract The production cost of materials for hydrogen storage is one of the major issues to be addressed in order to consider them suitable for large scale applications. In the last decades several authors reported on the hydrogen sorption properties of Mg and Mg-based systems. In this work magnesium industrial wastes of AZ91 alloy and Mg-10 wt.% Gd alloy are used for the production of hydrogen storage materials. The hydrogen sorption properties of the alloys were investigated by means of volumetric technique, in situ synchrotron radiation powder X-ray diffraction (SR-PXD) and calorimetric methods. The measured reversible hydrogen storage capacity for the alloys AZ91 and Mg-10 wt.% Gd are 4.2 and 5.8 wt.%, respectively. For the Mg-10 wt.% Gd alloy, the hydrogenated product was also successfully used as starting reactant for the synthesis of Mg(NH2)2 and as MgH2 substitute in the Reactive Hydride Composite (RHC) 2LiBH4 + MgH2. The results of this work demonstrate the concrete possibility to use Mg alloy wastes for hydrogen storage purposes.

C. Pistidda; N. Bergemann; J. Wurr; A. Rzeszutek; K.T. Møller; B.R.S. Hansen; S. Garroni; C. Horstmann; C. Milanese; A. Girella; O. Metz; K. Taube; T.R. Jensen; D. Thomas; H.P. Liermann; T. Klassen; M. Dornheim

2014-01-01T23:59:59.000Z

33

Nevada nuclear waste storage investigations: briefing book  

SciTech Connect

The Nevada Nuclear Waste Storage Investigations (NNWSI) are discussed briefly. The tuff in Yucca mountains being investigated as a possible repository host for radioactive wastes. The Spent Fuel Test-Climax began in the spring of 1980 in the northeastern Nevada Test Site about 1400 ft below the desert surface. The test has provided significant scientific and technical contributions in the following areas: heat impact on a large underground facility in a hard, brittle rock, impact of ventilation designs on repository heat removal, suitability and operational characteristics of instrumentation in a repository, impact of the mining procedures on underground openings and the surrounding rock, and heat and radiation effects on the physical, mechanical, and chemical properties of granite.

NONE

1983-03-01T23:59:59.000Z

34

Clean Cities: Waste-to-Wheels: Building for Success Workshop  

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

Events Events Printable Version Share this resource Send a link to Clean Cities: Waste-to-Wheels: Building for Success Workshop to someone by E-mail Share Clean Cities: Waste-to-Wheels: Building for Success Workshop on Facebook Tweet about Clean Cities: Waste-to-Wheels: Building for Success Workshop on Twitter Bookmark Clean Cities: Waste-to-Wheels: Building for Success Workshop on Google Bookmark Clean Cities: Waste-to-Wheels: Building for Success Workshop on Delicious Rank Clean Cities: Waste-to-Wheels: Building for Success Workshop on Digg Find More places to share Clean Cities: Waste-to-Wheels: Building for Success Workshop on AddThis.com... Conferences & Workshops Clean Cities 20th Anniversary Electric Vehicle Community Readiness Stakeholder Summit Waste-to-Wheels

35

EA-0874: Low-level Waste Drum Staging Building at Weapons Engineering  

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

74: Low-level Waste Drum Staging Building at Weapons 74: Low-level Waste Drum Staging Building at Weapons Engineering Tritium Facility, TA-16 Los Alamos National Laboratory, Los Alamos, New Mexico EA-0874: Low-level Waste Drum Staging Building at Weapons Engineering Tritium Facility, TA-16 Los Alamos National Laboratory, Los Alamos, New Mexico SUMMARY This EA evaluates the environmental impacts of a proposal to place a 3 meter (m) by 4.5 m prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium Facility at Technical Area 16, U.S. Department of Energy's Los Alamos National Laboratory in Los Alamos, New Mexico, and to use the building as a staging site for sealed 55-gallon drums of noncompactible waste contaminated with low levels of tritium. PUBLIC COMMENT OPPORTUNITIES

36

324 Building special-case waste assessment in support of the 324 Building closure (TPA milestone M-89-05)  

SciTech Connect

Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05 requires US Department of Energy, Richland Operations Office to complete a 324 Building Special Case Waste Assessment in Support of the 324 Building Closure. This document has been prepared with the intent of meeting this regulatory commitment. Alternatives for the Special Case Wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.

Hobart, R.L.

1998-05-12T23:59:59.000Z

37

Successfully Marketing Thermal Storage in Commercial Buildings  

E-Print Network (OSTI)

This paper first reviews the key hurdles to thermal energy storage. Next, case studies of three electric utility thermal storage marketing programs are reviewed. The results of these case studies. as well as advice and experiences from other...

McDonald, C.

1988-01-01T23:59:59.000Z

38

Modification and expansion of X-7725A Waste Accountability Facility for storage of polychlorinated biphenyl wastes at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio  

SciTech Connect

The US Department of Energy (DOE) must manage wastes containing polychlorinated biphenyls (PCBs) in accordance with Toxic Substances Control Act (TSCA) requirements and as prescribed in a Federal Facilities Compliance Agreement (FFCA) between DOE and the U.S. Environmental Protection Agency (EPA). PCB-containing wastes are currently stored in the PORTS process buildings where they are generated. DOE proposes to modify and expand the Waste Accountability facility (X-7725A) at the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio, to provide a central storage location for these wastes. The proposed action is needed to eliminate the fire and safety hazards presented by the wastes. In this EA, DOE considers four alternatives: (1) no action, which requires storing wastes in limited storage areas in existing facilities; (2) modifying and expanding the X-7725A waste accountability facility; (3) constructing a new PCB waste storage building; and (4) shipping PCB wastes to the K-25 TSCA incinerator. If no action is taken, PCB-contaminated would continue to be stored in Bldgs X-326, X-330, and X-333. As TSCA cleanup activities continue, the quantity of stored waste would increase, which would subsequently cause congestion in the three process buildings and increase fire and safety hazards. The preferred alternative is to modify and expand Bldg. X-7725A to store wastes generated by TSCA compliance activities. Construction, which could begin as early as April 1996, would last approximately five to seven months, with a total peak work force of 70.

NONE

1995-11-01T23:59:59.000Z

39

RADIOACTIVE WASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK-RESULTS OF FIELD INVESTIGATIONS AT STRIPA, SWEDEN  

E-Print Network (OSTI)

Waste Storage in Mined Caverns—Program Summary. LawrenceWASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK- BESULTS

Witherspoon, P.A.

2010-01-01T23:59:59.000Z

40

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

SciTech Connect

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

Note: This page contains sample records for the topic "waste storage building" 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

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents (OSTI)

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

42

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

SciTech Connect

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

43

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

J. D. Bigbee

2000-06-21T23:59:59.000Z

44

Electric Storage in California's Commercial Buildings  

E-Print Network (OSTI)

or combined heat and power (CHP) in commercial buildings anda renewable energy source or CHP system at the commercialPV at (GW) microgrids adopted CHP and (GW) DG at microgrids

Stadler, Michael

2014-01-01T23:59:59.000Z

45

SWEDISH-AMERICAN COOPERATIVE PROGRAM ON RADIOACTIVE WASTE STORAGE IN MINED CAVERNS. PROGRAM SUMMARY  

E-Print Network (OSTI)

WASTE STORAGE IN MINED CAVERNS by P. A. Witherspoon LawrenceWASTE STORAGE IN MINED CAVERNS INTRODUCTION Final and safeon the possibility of using mined caverns in salt as waste

Witherspoon, P.A.

2011-01-01T23:59:59.000Z

46

Waste Panel Expected to Back Interim Storage  

Science Journals Connector (OSTI)

...a nuclear waste repository at Yucca Mountain, Nevada, last year, President...Then it would be shipped to Yucca Mountain, transferred into steel cylinders...licensed. One reason was that Yucca Mountain had to cool waste before permanently...

Eli Kintisch

2011-07-08T23:59:59.000Z

47

Waste Encapsulation and Storage Facility - Hanford Site  

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

of heat were removed from the high level waste tanks at Hanford. Called cesium and strontium, these elements had to be taken out of single shell waste tanks to reduce the...

48

Aluminum phosphate ceramics for waste storage  

SciTech Connect

The present disclosure describes solid waste forms and methods of processing waste. In one particular implementation, the invention provides a method of processing waste that may be particularly suitable for processing hazardous waste. In this method, a waste component is combined with an aluminum oxide and an acidic phosphate component in a slurry. A molar ratio of aluminum to phosphorus in the slurry is greater than one. Water in the slurry may be evaporated while mixing the slurry at a temperature of about 140-200.degree. C. The mixed slurry may be allowed to cure into a solid waste form. This solid waste form includes an anhydrous aluminum phosphate with at least a residual portion of the waste component bound therein.

Wagh, Arun; Maloney, Martin D

2014-06-03T23:59:59.000Z

49

Building Hierarchical Grid Storage Using the GFARM Global File System  

E-Print Network (OSTI)

-sharing service and the GFARM grid file system; then, it introduces our hybrid architecture. Section 4 gives Work One of the major goals of grid infrastructures is to transparently provide access to comBuilding Hierarchical Grid Storage Using the GFARM Global File System and the JUXMEM Grid Data

Paris-Sud XI, Université de

50

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities  

SciTech Connect

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

Sasser, K.

1994-06-01T23:59:59.000Z

51

TRU waste certification compliance requirements for contact-handled wastes retrieved from storage for shipment to the WIPP  

SciTech Connect

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE Orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste.

Not Available

1982-09-01T23:59:59.000Z

52

Independent Oversight Activity Report, Savannah River Site Waste Solidification Building  

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

Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design [HIAR SRS-2013-5-07

53

REPORT OF SURVEY OF OAK RIDGE BUILDING 3597 HOT STORAGE GARDEN  

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

BUILDING 3597 HOT STORAGE GARDEN U.S. Department of Energy Office of Environmental Management & Office of Science Report of Survey of Oak Ridge Building 3597 Hot Storage Garden...

54

United States National Waste Terminal Storage argillaceous rock studies  

SciTech Connect

The past and present argillaceous rock studies for the US National Waste Terminal Storage Program consist of: (1) evaluation of the geological characteristics of several widespread argillaceous formations in the United States; (2) laboratory studies of the physical and chemical properties of selected argillaceous rock samples; and (3) two full-scale in situ surface heater experiments that simulate the emplacement of heat-generating radioactive waste in argillaceous rock.

Brunton, G.D.

1981-01-01T23:59:59.000Z

55

Waste-heat recovery in batch processes using heat storage  

SciTech Connect

The waste-heat recovery in batch processes has been studied using the pinch-point method. The aim of the work has been to investigate theoretical and practical approaches to the design of heat-exchanger networks, including heat storage, for waste-heat recovery in batch processes. The study is limited to the incorporation of energy-storage systems based on fixed-temperature variable-mass stores. The background for preferring this to the alternatives (variable-temperature fixed-mass and constant-mass constant-temperature (latent-heat) stores) is given. It is shown that the maximum energy-saving targets as calculated by the pinch-point method (time average model, TAM) can be achieved by locating energy stores at either end of each process stream. This theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. A simple procedure for determining a number of heat-storage tanks sufficient to achieve the maximum energy-saving targets as calculated by the pinch-point method is described. This procedure relies on combinatorial considerations, and could therefore be labeled the combinatorial method for incorporation of heat storage in heat-exchanger networks. Qualitative arguments justifying the procedure are presented. For simple systems, waste-heat recovery systems with only three heat-storage temperatures (a hot storage, a cold storage, and a heat store at the pinch temperature) often can achieve the maximum energy-saving targets. Through case studies, six of which are presented, it is found that a theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. The description of these six cases is intended to be sufficiently detailed to serve as benchmark cases for development of alternative methods.

Stoltze, S.; Mikkelsen, J.; Lorentzen, B.; Petersen, P.M.; Qvale, B. [Technical Univ. of Denmark, Lyngby (Denmark). Lab. for Energetics

1995-06-01T23:59:59.000Z

56

An Adaptive, Consent-Based Path to Nuclear Waste Storage and...  

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

An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions February 12, 2014 -...

57

Impact of earthen waste storage on nitrate concentration of surface water  

Science Journals Connector (OSTI)

One of the major sources of nitrogen is animal waste stored in earthen waste storage or unlined storage ponds. Quantifying seepage and mass transport of ... is the first critical step in estimating the long-term ...

Tasuku Kato; Motoko Shimura

2007-09-01T23:59:59.000Z

58

U.S. Department of Energy Awards Contracts for Waste Storage...  

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

Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis...

59

Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain, Nevada  

E-Print Network (OSTI)

was heated to replicate the effects of long-term storage of decaying nuclear waste and to study the effects for the long- term storage of high-level nuclear waste from reactors and decom- missioned atomic weaponsSeismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain

Snieder, Roel

60

Extended storage of low-level radioactive waste: an update  

SciTech Connect

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) has contracted with Brookhaven National Laboratory to address the technical issues of extended storage. The dual objectives of this study are (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. The circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Luminescence dosimetry using building materials and personal objects  

Science Journals Connector (OSTI)

......case of a radioactive waste storage facility(38). Since...have some potential for long-term dosimetry, further investigation...release of radioactive wastes into the Techa river...quartz from a radioactive waste storage building. Radiat. Prot......

H. Y. Göksu; I. K. Bailiff

2006-09-01T23:59:59.000Z

62

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

SciTech Connect

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

63

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

64

Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste  

Science Journals Connector (OSTI)

......an interim storage facility for nuclear waste Burkhard Heuel-Fabianek Ralf...Research Centre Julich, Germany, nuclear waste is stored in drums and other vessels...Research Centre Julich (FZJ) nuclear waste is generated, which has to be......

Burkhard Heuel-Fabianek; Ralf Hille

2005-12-20T23:59:59.000Z

65

Hanford facility dangerous waste permit application, PUREX storage tunnels  

SciTech Connect

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

66

Pipe overpack container for trasuranic waste storage and shipment  

DOE Patents (OSTI)

A Pipe Overpack Container for transuranic waste storage and shipment. The system consists of a vented pipe component which is positioned in a vented, insulated 55 gallon steel drum. Both the vented pipe component and the insulated drum are capable of being secured to prevent the contents from leaving the vessel. The vented pipe component is constructed of 1/4 inch stainless steel to provide radiation shielding. Thus, allowing shipment having high Americium-241 content. Several Pipe Overpack Containers are then positioned in a type B, Nuclear Regulatory Commission (NRC) approved, container. In the current embodiment, a TRUPACT-II container was employed and a maximum of fourteen Pipe Overpack Containers were placed in the TRUPACT-II. The combination received NRC approval for the shipment and storage of transuranic waste.

Geinitz, Richard R. (Arvada, CO); Thorp, Donald T. (Broomfield, CO); Rivera, Michael A. (Boulder, CO)

1999-01-01T23:59:59.000Z

67

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

68

Computational Study on Thermal Properties of HVAC System with Building Structure Thermal Storage  

E-Print Network (OSTI)

Building structure thermal storage (BSTS) HVAC systems can store heat during nighttime thermal storage operation (nighttime operation hours) by using off-peak electricity and release it in the daytime air-conditioning operation (daytime operation...

Sato, Y.; Sagara, N.; Ryu, Y.; Maehara, K.; Nagai, T.

2007-01-01T23:59:59.000Z

69

Stamp out energy waste | ENERGY STAR Buildings & Plants  

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

Stamp out energy waste Stamp out energy waste Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section Learn the benefits Get started Use Portfolio Manager Save energy Stamp out energy waste Find cost-effective investments Engage occupants Purchase energy-saving products Put computers to sleep Get help from an expert Take a comprehensive approach Install renewable energy systems

70

Integrated Building Energy Systems Design Considering Storage Technologies  

E-Print Network (OSTI)

L ABORATORY Integrated Building Energy Systems Design7301 Integrated building energy systems design considering

Stadler, Michael

2009-01-01T23:59:59.000Z

71

Cooling Strategies Based on Indicators of Thermal Storage in Commercial Building Mass  

E-Print Network (OSTI)

specific instance of this phenomenon, in which thermal storage by building mass over weekends exacerbates Monday cooling energy requirements. The study relies on computer simulations of energy use for a large, office building prototype in El Paso, TX using...

Eto, J. H.

1985-01-01T23:59:59.000Z

72

Fire protection guide for solid waste metal drum storage  

SciTech Connect

This guide provides a method to assess potential fire development in drum storage facilities. The mechanism of fire propagation/spread through stored drum arrays is a complex process. It involves flame heat transfer, transient conduction,convection, and radiation between drums (stored in an array configuration). There are several phenomena which may occur when drums are exposed to fire. The most dramatic is violent lid failure which results in total lid removal. When a drum loses its lid due to fire exposure, some or all of the contents may be ejected from the drum, and both the ejected combustible material and the combustible contents remaining within the container will burn. The scope of this guide is limited to storage arrays of steel drums containing combustible (primarily Class A) and noncombustible contents. Class B combustibles may be included in small amounts as free liquid within the solid waste contents.Storage arrays, which are anticipated in this guide, include single or multi-tier palletized (steel or wood pallets) drums,high rack storage of drums, and stacked arrays of drums where plywood sheets are used between tiers. The purpose of this guide is to describe a simple methodology that estimates the consequences of a fire in drum storage arrays. The extent of fire development and the resulting heat release rates can be estimated. Release fractions applicable to this type of storage are not addressed, and the transport of contaminants away from the source is not addressed. However, such assessments require the amount of combustible material consumed and the surface area of this burning material. The methods included in this guide do provide this information.

Bucci, H.M.

1996-09-16T23:59:59.000Z

73

Integrated mixed waste storage program for spent solvent and laboratory waste  

SciTech Connect

A new tank project was initiated to provide a facility capable of providing the necessary storage capacity while meeting the South Carolina Hazardous Waste Management Regulations. The new project was initiated as a Category 11, General Plant Project. This project funding strategy would have allowed SRS access to project funding without Congressional approval as a Line Item, permitting the use of an expedited schedule for design and construction. The project team and Department of Energy -- Savannah River were successful in obtaining FY94 Line Item funding for the new tank project. However, the operational date for the new tank project was extended to October 1996. The revised facility operational date did not support the date submitted to South Carolina Department of Heath and Environmental Control as part of the existing facility closure plan. A plan to alleviate the South Carolina Department of Heath and Environmental Control concerns with the SRS existing tanks system had to be developed prior to notifying the state that the operational date was extended to October 1996. The remainder of this paper presents the plan that was developed and presented to the South Carolina Department of Heath and Environmental Control. The SRS integrated mixed waste storage program is divided into three separate phase: (1) interim waste storage for the period between facility closure and operation of the new tank facility, (2) closure of the existing facility and (3) the new solvent storage facility.

Walker, C.M.

1994-03-01T23:59:59.000Z

74

Robotics for waste storage inspection: A user`s perspective  

SciTech Connect

Self-navigating robotic vehicles are now commercially available, and the technology supporting other important system components has also matured. Higher reliability and the obtainability of system support now make it practical to consider robotics as a way of addressing the growing operational requirement for the periodic inspection and maintenance of radioactive, hazardous, and mixed waste inventories. This paper describes preparations for the first field deployment of an autonomous container inspection robot at a Department of Energy (DOE) site. The Stored Waste Autonomous Mobile Inspector (SWAMI) is presently being completed by engineers at the Savannah River Technology Center (SRTC). It is a modified version of a commercially available robot. It has been outfitted with sensor suites and cognition that allow it to perform inspections of drum inventories and their storage facilities.

Hazen, F.B.

1994-06-23T23:59:59.000Z

75

Integrated Building Energy Systems Design Considering Storage Technologies  

E-Print Network (OSTI)

among PV, solar thermal, and storage systems can be complex,and solar thermal collectors; electrical storage, flow8, huge PV, solar thermal as well as storage systems will be

Stadler, Michael

2009-01-01T23:59:59.000Z

76

SRS Waste Solidification Building Project Peer Review, July 2011  

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

SRS-2011-07-15 SRS-2011-07-15 Site: Savannah River Site, NA-26 Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Waste Solidification Building Project Peer Review Dates of Activity : 07/12/2011 - 07/15/2011 Report Preparer: James Lockridge Activity Description/Purpose: At the request of the National Nuclear Security Administration (NNSA) Office of Enterprise Project Management (NA- APM-20), the Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), provided an expert to review the Waste Solidification Building (WSB) startup programs and procedures associated with worker safety and health, environment, and security. Criteria for the review was detailed in the Criteria,

77

Comparison of carbon dioxide and nuclear waste storage costs in Lithuania  

Science Journals Connector (OSTI)

Nuclear power and carbon capture and storage (CCS) are key greenhouse gas mitigation options under consideration across the world. Both technologies imply long-term waste management challenge. Geological storage of carbon dioxide (CO2) and nuclear waste has much in common, and valuable lessons can be learnt from a comparison. Seeking to compare these technologies economic, social and environmental criteria need to be selected and expressed in terms of indicators. Very important issue is costs and economics of geological storage of carbon dioxide and nuclear waste. The costs of storage are one of the main indicators for assessment of technologies in terms of economic criteria. The paper defines the costs of the geological storage of CO2 and nuclear waste in Lithuania, drawing also on insights from other parts of the world. The costs of carbon dioxide and nuclear waste storage are evaluated in UScnt/kWh and compared. The paper critically compares the characteristics and location of the both sources of and storage options for CO2 and nuclear waste in Lithuania. It discusses the main costs categories for carbon dioxide and nuclear waste storage. The full range of potential geological storage options is considered and the most reliable options for carbon dioxide and nuclear waste are selected for the comparative costs assessment.

Dalia Streimikiene

2012-01-01T23:59:59.000Z

78

Experiences in Building an Object-Based Storage System based on the OSD T-10 Standard  

E-Print Network (OSTI)

Experiences in Building an Object-Based Storage System based on the OSD T-10 Standard David Du and management costs, object based storage is on the verge of becoming the next standard storage interface. The American National Standards Institute (ANSI) ratified the object based stor- age interface standard (also

Minnesota, University of

79

Experiences Building an Object-Based Storage System based on the OSD T-10 Standard  

E-Print Network (OSTI)

Experiences Building an Object-Based Storage System based on the OSD T-10 Standard David Du costs, object based storage is on the verge of becoming the next standard storage interface. The American National Standards Institute (ANSI) ratified the object based stor- age interface standard (also

Jeong, Jaehoon "Paul"

80

Potentials of Demand Side Management Using Heat Pumps with Building Mass as a Thermal Storage  

Science Journals Connector (OSTI)

Abstract Within this work, load-shifting possibilities of heat pumps in residential buildings as well as its influencing and limiting factors are displayed. The intermediate storage is achieved by using the thermal mass of the building so the heat supply can be postponed from the heat demand for a certain period, depending on the characteristics of the building. No additional water storage is considered.

Charlotte Ellerbrok

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Analysis of Heat Charging and Discharging on the Phase Change Energy-Storage Composite Wallboard (PCECW) in Building  

E-Print Network (OSTI)

This research paper combines the phase change material and the basal building material to constitute a kind of new phase change energy- storage composite wallboard (PCECW), applied in a residential building in Beijing. We analyzed the energy-storage...

Yue, H.; Chen, C.; Liu, Y.; Guo, H.

2006-01-01T23:59:59.000Z

82

Trade-off between collector area, storage volume, and building conservation in annual-storage solar-heating systems  

SciTech Connect

Annual storage is used with active solar heating systems to permit storage of summertime solar heat for winter use. The results of a comprehensive computer simulation study of the performance of active solar heating systems with long-term hot water storage are presented. A unique feature of this study is the investigation of systems used to supply backup heat to passive solar and energy-conserving buildings, as well as to meet standard heating and hot water loads. Findings show that system output increases linearly as storage volume increases, up to the point where the storage tank is large enough to store all heat collected in summer. This point, the point of unconstrained operation, is the likely economic optimum. Unlike diurnal storage systems, annual storage systems show only slightly diminished efficiency as system size increases. Annual storage systems providing nearly 100% solar space heat may cost the same or less per unit heat delivered as a 50% diurnal solar system. Also in contrast to diurnal systems, annual storage systems perform efficiently in meeting the load of a passive or energy-efficient building.

Sillman, S.

1981-04-01T23:59:59.000Z

83

EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage  

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

42: Return of Isotope Capsules to the Waste Encapsulation and 42: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts of the proposal for the return of all leased cesium-137 and strontium-90 leased capsules to the U.S. Department of Energy's Waste Encapsulation and Storage Facility on the Hanford Site, to ensure safe management and storage, pending final disposition. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD May 11, 1994 EA-0942: Finding of No Significant Impact Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington

84

EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power  

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

0: Radiological Work and Storage Building at the Knolls 0: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York Summary The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors. Public Comment Opportunities None available at this time. Documents Available for Download July 16, 2012

85

Press Release Von Roll Inova to build the UK's largest energy-from-waste  

E-Print Network (OSTI)

, and regenerative heat recovery is used to boost the plant's overall energy efficiency. The majority of the wastePress Release Von Roll Inova to build the UK's largest energy-from-waste plant Zürich, September, 1 Roll Inova will build the UK's largest energy-from-waste facility. The contract is worth approximately

Columbia University

86

TRU waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the WIPP. Revision 1  

SciTech Connect

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 2 refs., 1 fig.

Not Available

1985-09-01T23:59:59.000Z

87

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

88

Integrated Building Energy Systems Design Considering Storage Technologies  

E-Print Network (OSTI)

lead/acid battery, and thermal storage, capabilities, withn/a n/a electrical flow battery I) thermal I) Flow batteriesor $/kWh) lifetime (a) thermal storage 8 IV) flow battery V)

Stadler, Michael

2009-01-01T23:59:59.000Z

89

Soil load above Hanford waste storage tanks (2 volumes)  

SciTech Connect

This document is a compilation of work performed as part of the Dome Load Control Project in 1994. Section 2 contains the calculations of the weight of the soil over the tank dome for each of the 75-feet-diameter waste-storage tanks located at the Hanford Site. The chosen soil specific weight and soil depth measured at the apex of the dome crown are the same as those used in the primary analysis that qualified the design. Section 3 provides reference dimensions for each of the tank farm sites. The reference dimensions spatially orient the tanks and provide an outer diameter for each tank. Section 4 summarizes the available soil surface elevation data. It also provides examples of the calculations performed to establish the present soil elevation estimates. The survey data and other data sources from which the elevation data has been obtained are printed separately in Volume 2 of this Supporting Document. Section 5 contains tables that provide an overall summary of the present status of dome loads. Tables summarizing the load state corresponding to the soil depth and soil specific weight for the original qualification analysis, the gravity load requalification for soil depth and soil specific weight greater than the expected actual values, and a best estimate condition of soil depth and specific weight are presented for the Double-Shell Tanks. For the Single-Shell Tanks, only the original qualification analysis is available; thus, the tabulated results are for this case only. Section 6 provides a brief overview of past analysis and testing results that given an indication of the load capacity of the waste storage tanks that corresponds to a condition approaching ultimate failure of the tank. 31 refs.

Pianka, E.W. [Advent Engineering Services, Inc., San Ramon, CA (United States)

1995-01-25T23:59:59.000Z

90

DOE/EA-0820 ENVIRONMENTAL ASSESSMENT Construction of Mixed Waste Storage RCRA Facilities,  

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

20 20 ENVIRONMENTAL ASSESSMENT Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669 u.s. Department of Energy Oak Ridge National Laboratory Oak Ridge, Tennessee April 1994 ER t>ISTRf8UT!Q~~ Or-~I-:r8 DOCUMENT IS UNLlMIT~ DISCLAIMER This report was .prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial

91

EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington  

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

The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

92

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

M. D. Staiger

1999-06-01T23:59:59.000Z

93

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and 8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) 18HIB - RCRAHazardousWasteTreatmentStorageAndDisposalPermitTSD.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Health Solid and Hazardous Waste Branch United States Environmental Protection Agency Regulations & Policies Resource Conversation and Recovery Act (42 U.S.C. 6901, et seq.) 40 CFR 270 Hawaii Administrative Rules Title 11, Chapter 261 Hawaii Administrative Rules Title 11, Chapter 265 Triggers None specified Click "Edit With Form" above to add content

94

SORPTION OF URANIUM, PLUTONIUM AND NEPTUNIUM ONTO SOLIDS PRESENT IN HIGH CAUSTIC NUCLEAR WASTE STORAGE TANKS  

SciTech Connect

Solids such as granular activated carbon, hematite and sodium phosphates, if present as sludge components in nuclear waste storage tanks, have been found to be capable of precipitating/sorbing actinides like plutonium, neptunium and uranium from nuclear waste storage tank supernatant liqueur. Thus, the potential may exists for the accumulation of fissile materials in such nuclear waste storage tanks during lengthy nuclear waste storage and processing. To evaluate the nuclear criticality safety in a typical nuclear waste storage tank, a study was initiated to measure the affinity of granular activated carbon, hematite and anhydrous sodium phosphate to sorb plutonium, neptunium and uranium from alkaline salt solutions. Tests with simulated and actual nuclear waste solutions established the affinity of the solids for plutonium, neptunium and uranium upon contact of the solutions with each of the solids. The removal of plutonium and neptunium from the synthetic salt solution by nuclear waste storage tank solids may be due largely to the presence of the granular activated carbon and transition metal oxides in these storage tank solids or sludge. Granular activated carbon and hematite also showed measurable affinity for both plutonium and neptunium. Sodium phosphate, used here as a reference sorbent for uranium, as expected, exhibited high affinity for uranium and neptunium, but did not show any measurable affinity for plutonium.

Oji, L; Bill Wilmarth, B; David Hobbs, D

2008-05-30T23:59:59.000Z

95

Investigation of Latent-Heat Storage Systems for Green Building Applications  

Science Journals Connector (OSTI)

In green building applications, highest energy demands are needed for air conditioning to ... heat storage systems during the usage of solar energy and ground-sourced heat pump systems for ... period, analyses sh...

Devrim Aydin; Zafer Utlu; Olcay Kincay

2014-01-01T23:59:59.000Z

96

Building of multilevel stakeholder consensus in radioactive waste repository siting  

SciTech Connect

This report considers the problem of multilevel consensus building for siting and construction of shared multinational/regional repositories for radioactive waste (RW) deep disposal. In the siting of a multinational repository there appears an essential innovative component of stakeholder consensus building, namely: to reach consent - political, social, economic, ecological - among international partners, in addition to solving the whole set of intra-national consensus building items. An entire partnering country is considered as a higher-level stakeholder - the national stakeholder, represented by the national government, being faced to simultaneous seeking an upward (international) and a downward (intra-national) consensus in a psychologically stressed environment, possibly being characterized by diverse political, economic and social interests. The following theses as a possible interdisciplinary approach towards building of shared understanding and stakeholder consensus on the international scale of RW disposal are forwarded and developed: a) building of international stakeholder consensus would be promoted by activating and diversifying on the international scale multilateral interactions between intra- and international stakeholders, including web-based networks of the RW disposal site investigations and decision-making, as well as networks for international cooperation among government authorities in nuclear safety, b) gradual progress in intergovernmental consensus and reaching multilateral agreements on shared deep repositories will be the result of democratic dialogue, via observing the whole set of various interests and common resolving of emerged controversies by using advanced synergetic approaches of conflict resolution, c) cross-cultural thinking and world perception, mental flexibility, creativity and knowledge are considered as basic prerogatives for gaining a higher level of mutual understanding and consensus for seeking further consensus, for advancing the preparedness to act together, and ultimately - for achieving desired shared goals. It is proposed that self-organized social learning will make it possible to promote adequate perception of risk and prevent, by diminishing uncertainties and unknown factors, social amplification of an imagined risk, as well as to increase the trust level and facilitate more adequate equity perception. The proposed approach to the multilevel stakeholder consensus building on international scale is extrapolated to the present-day activities of siting of such near-surface RW disposal facilities which supposedly could have non-negligible trans-boundary impact. A multilevel stakeholder interaction process is considered for the case of resolving of emerged problems in site selection for the planned near-surface RW repository in vicinity of the Lithuanian-Latvian border foreseen for disposal of short lived low- and intermediate level waste arising from the decommissioning of the Ignalina Nuclear Power Plant. (authors)

Dreimanis, A. [Radiation Safety Centre, Riga LV (Latvia)

2007-07-01T23:59:59.000Z

97

TRU (transuranic) waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the Waste Isolation Pilot Plant: Revision 2  

SciTech Connect

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for acceptance of newly generated CH waste to be shipped to the WIPP are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig.

Not Available

1989-01-01T23:59:59.000Z

98

Experimental Investigation of Direct Expansion Dynamic Ice-on-coil Storage System Used in Residential Buildings  

E-Print Network (OSTI)

The reduction in electricity consumption of an ice-storage system in the daytime leads to financial savings for building owners and extension savings for a power plant and national economy. Great advancements have been made in domestic ice-storage...

Zheng, M.; Kong, F.; Han, Z.; Liu, W.

2006-01-01T23:59:59.000Z

99

Nuclear Waste Storage in Gel-Derived Materials  

Science Journals Connector (OSTI)

For long life nuclear wastes (essentially actinides) research is in progress ... a process to prepare silica glass embedding the nuclear waste. Porous silica (gel) is used as a host matrix for nuclear waste. Neod...

T. Woignier; J. Reynes; J. Phalippou…

2000-12-01T23:59:59.000Z

100

Characterization of past and present waste streams from the 325 Radiochemistry Building  

SciTech Connect

The purpose of this report is to characterize, as far as possible, the solid waste generated by the 325 Radiochemistry Building since its construction in 1953. Solid waste as defined in this document is any containerized or self-contained material that has been declared waste. This characterization is of particular interest in the planning of transuranic (TRU) waste retrieval operations including the Waste Receiving and Processing (WRAP) Facility. Westinghouse Hanford Company (Westinghouse Hanford) and Battelle Pacific Northwest Laboratory (PNL) activities at Building 325 have generated approximately 4.4% and 2.4%, respectively, of the total volume of TRU waste currently stored at the Hanford Site.

Pottmeyer, J.A.; Weyns-Rollosson, M.I.; Dicenso, K.D.; DeLorenzo, D.S. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING In general, building materials contain low levels of radioactivity. For example, the range of  

E-Print Network (OSTI)

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING MATERIALS In general, building materials contain low, especially in buildings constructed with materials containing uranium TENORM mine wastes. In the Grand the wastes from uranium mines have been removed from mining sites and used in local and nearby communities

102

Composite analysis for solid waste storage area 6  

SciTech Connect

The composite analysis (CA) provides an estimate of the potential cumulative impacts to a hypothetical future member of the public from the Solid Waste Storage Area 6 (SWSA 6) disposal operations and all of the other sources of radioactive material in the ground on the ORR that may interact with contamination originating in SWSA 6.The projected annual dose to hypothetical future member of the public from all contributing sources is compared to the primary dose limit of 100 mrem per year and a dose constraint of 30 mrem per year. Consistent with the CA guidance, dose estimates for the first 1000 years after disposal are emphasized for comparison with the primary dose limit and dose constraint.The current land use plan for the ORR is being revised, and may include a reduction in the land currently controlled by DOE on the ORR. The possibility of changes in the land use boundary is considered in the CA as part of the sensitivity and uncertainty analysis of the results, the interpretation of results, and the conclusions.

Lee, D.W.

1997-09-01T23:59:59.000Z

103

Use of Thermal Energy Storage to Enhance the Recovery and Utilization of Industrial Waste Heat  

E-Print Network (OSTI)

evaluation involving process data from 12 industrial plants to determine if thermal energy storage (TES) systems can be used with commercially available energy management equipment to enhance the recovery and utilization of industrial waste heat. Results...

McChesney, H. R.; Bass, R. W.; Landerman, A. M.; Obee, T. N.; Sgamboti, C. T.

1982-01-01T23:59:59.000Z

104

Radiation Damage of Glasses for Nuclear Waste Storage: Optical and Microstructural Aspects  

Science Journals Connector (OSTI)

A possible way to achieve a stable nuclear waste form consists of incorporating the different radionuclides ... actinides, radiation damage is produced in the storage matrix, which may potentially affect its long-term

M. Antonini; P. Camagni; A. Manara; M. Sacchi

1985-01-01T23:59:59.000Z

105

Rutherford backscattering for measuring corrosion layers on glasses for long-term storage of radioactive waste  

Science Journals Connector (OSTI)

The method considered safest for isolation of nuclear waste is vitrification (solidification in a glass or glassceramic matrix) with long-term storage in stable geological repositories. Borosilicate glasses are ....

Hj. Matzke

1984-01-01T23:59:59.000Z

106

Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building  

SciTech Connect

This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities.

Lata

1996-09-26T23:59:59.000Z

107

Alternate airborne release fraction determination for hazardous waste management storage repository hazard categorization at the Lawrence Livermore National Laboratory  

SciTech Connect

Hazardous Waste Management (HWM) facilities are used in the handling and processing of solid and liquid radioactive, hazardous, mixed, and medical wastes generated at Lawrence Livermore National Laboratory (LLNL). Waste may be treated or stored in one of the HWM facility units prior to shipment off site for treatment or disposal. Planned facilities such as the Decontamination and Waste Treatment Facility (DWTF) and the Building 280 Container Storage Unit are expected to handle similar waste streams. A hazard classification was preformed in each facility safety analysis report (SAR) according to the DOE Standard 1027-92 `Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports.` The general methodology practiced by HWM to determine alternate airborne release fractions (ARFs) in those SARs was based upon a beyond evaluation basis earthquake accident scenario characterized by the release of the largest amount of respirable, airborne radioactive material. The alternate ARF was calculated using a three-factor formula consisting of the fraction of failed waste containers, fraction of material released from failed waste containers,and the fraction of material entrained to the environment. Recently, in deliberation with DOE-Oakland representatives, HWM decided to modify this methodology. In place of the current detailed analysis, a more straightforward process was proposed based upon material form, credible accident environments, and empirical data. This paper will discuss the methodology and derivation of ARFs specific to HWM treatment and storage facilities that are alternative to those presented in DOE-STD-1027-92.

Brumburgh, G.P.

1998-05-01T23:59:59.000Z

108

Predictive Optimal Control of Active and Passive Building Thermal Storage Inventory  

SciTech Connect

Cooling of commercial buildings contributes significantly to the peak demand placed on an electrical utility grid. Time-of-use electricity rates encourage shifting of electrical loads to off-peak periods at night and weekends. Buildings can respond to these pricing signals by shifting cooling-related thermal loads either by precooling the building's massive structure or the use of active thermal energy storage systems such as ice storage. While these two thermal batteries have been engaged separately in the past, this project investigates the merits of harnessing both storage media concurrently in the context of predictive optimal control. This topical report describes the demonstration of the model-based predictive optimal control for active and passive building thermal storage inventory in a test facility in real-time using time-of-use differentiated electricity prices without demand charges. The laboratory testing findings presented in this topical report cover the second of three project phases. The novel supervisory controller successfully executed a three-step procedure consisting of (1) short-term weather prediction, (2) optimization of control strategy over the next planning horizon using a calibrated building model, and (3) post-processing of the optimal strategy to yield a control command for the current time step that can be executed in the test facility. The primary and secondary building mechanical systems were effectively orchestrated by the model-based predictive optimal controller in real-time while observing comfort and operational constraints. The findings reveal that when the optimal controller is given imperfect weather fore-casts and when the building model used for planning control strategies does not match the actual building perfectly, measured utility costs savings relative to conventional building operation can be substantial. This requires that the facility under control lends itself to passive storage utilization and the building model includes a realistic plant model. The savings associated with passive building thermal storage inventory proved to be small be-cause the test facility is not an ideal candidate for the investigated control technology. Moreover, the facility's central plant revealed the idiosyncratic behavior that the chiller operation in the ice-making mode was more energy efficient than in the chilled-water mode. Field experimentation (Phase III) is now required in a suitable commercial building with sufficient thermal mass, an active TES system, and a climate conducive to passive storage utilization over a longer testing period to support the laboratory findings presented in this topical report.

Gregor P. Henze; Moncef Krarti

2003-12-17T23:59:59.000Z

109

Page 1 of 3 Building or Facility Demolition / Waste Hauling Contractor  

E-Print Network (OSTI)

Page 1 of 3 Building or Facility Demolition / Waste Hauling Contractor Prequalification Procedures member, of a facility together with any related handling operations or the intentional burning held (e.g. PA Residual and Municipal Waste Hauling, etc.). If your company does not haul waste simply

Yener, Aylin

110

ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and  

E-Print Network (OSTI)

, The Texas A&M University System. #12;Pumping Pumping from the lagoon should be conducted annually, at least the designed life of sludge storage, frequent agitation and pumping may be necessary. In addition, solidsL ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage

Mukhtar, Saqib

111

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

M. D. Staiger

2007-06-01T23:59:59.000Z

112

ENERGY EFFICIENT BUILDING DESIGN AND THERMAL ENERGY STORAGE  

Science Journals Connector (OSTI)

This chapter discusses the potential for cost-effectively reducing the energy intensity of office buildings by applying proven technologies, especially the use of ground source systems with thermal energy stor...

Edward Morofsky

2007-01-01T23:59:59.000Z

113

SUSTAINABILITY OPPORTUNITY Waste audits from campus buildings reveal that 30% of the trash Stanford sends to the landfill is  

E-Print Network (OSTI)

How To... SUSTAINABILITY OPPORTUNITY Waste audits from campus buildings reveal that 30 on campus have active composting programs. Interested buildings and departments can start a voluntary office;MORE INFORMATION SUSTAINABLE STANFORD'S WASTE REDUCTION EFFORTS http://sustainable

Straight, Aaron

114

ALARA Analysis for Shippingport Pressurized Water Reactor Core 2 Fuel Storage in the Canister Storage Building (CSB)  

E-Print Network (OSTI)

The addition of Shippingport Pressurized Water Reactor (PWR) Core 2 Blanket Fuel Assembly storage in the Canister Storage Building (CSB) will increase the total cumulative CSB personnel exposure from receipt and handling activities. The loaded Shippingport Spent Fuel Canisters (SSFCs) used for the Shippingport fuel have a higher external dose rate. Assuming an MCO handling rate of 170 per year (K East and K West concurrent operation), 24-hr CSB operation, and nominal SSFC loading, all work crew personnel will have a cumulative annual exposure of less than the 1,000 mrem limit.

Lewis, M E

2000-01-01T23:59:59.000Z

115

Vermont Yankee experience with interim storage of low level radioactive waste in concrete modules  

SciTech Connect

This paper discusses the implementation of interim storage of low level radioactive waste using concrete modules at the Vermont Yankee Nuclear Power Station in Vernon, Vermont. Under the threat of possible loss of disposal capability in 1986, Vermont Yankee first considered the on-site storage option in 1985. prior to settling on a design, an investigation and economic analysis was performed of several designs. Modular concrete storage on a gravel pad was chosen as the most economical and the one providing the greatest flexibility. The engineering work, safety analysis, and pad construction were completed in 1985. Because of the passage of the Low Level Radioactive Waste Policy amendments Act in 1985, the loss of disposal capability did not occur in 1986. However, because the State of Vermont failed to meet the milestones of the Amendments Act, Vermont Yankee was restricted from the existing disposal sites on January 31, 1989. As a result, modules were purchased and waste was stored on site from 1989 until 1991. In 1991, the State of Vermont came back into compliance with the Amendments Act, and all waste stored on-site was shipped for burial. During the storage period 2 types of modules (1 box type and 1 cylinder type) were used. Lessons were learned, and changes were made to better control the off-site dose contribution of the waste. Recommendations are made to enhance the usability of the facility, such s lighting power, phones, etc. A shortcoming of the module storage concept is the inability to move waste during inclement weather. Despite this, the modules have provided an economical, technically sound, method of waste storage. The storage pad has not been used since 1991, but work is under way to review, and update as necessary, the safety analysis and procedures in preparation for reuse of the on-site storage facility after June 30, 1994.

Berger, S.; Weyman, D. [Vermont Yankee Nuclear Power Corporation, Vernon, VT (United States)

1995-05-01T23:59:59.000Z

116

Evaluation of distributed building thermal energy storage in conjunction with wind and solar electric power generation  

Science Journals Connector (OSTI)

Abstract Energy storage is often seen as necessary for the electric utility systems with large amounts of solar or wind power generation to compensate for the inability to schedule these facilities to match power demand. This study looks at the potential to use building thermal energy storage as a load shifting technology rather than traditional electric energy storage. Analyses are conducted using hourly electric load, temperature, wind speed, and solar radiation data for a 5-state central U.S. region in conjunction with simple computer simulations and economic models to evaluate the economic benefit of distributed building thermal energy storage (TES). The value of the TES is investigated as wind and solar power generation penetration increases. In addition, building side and smart grid enabled utility side storage management strategies are explored and compared. For a relative point of comparison, batteries are simulated and compared to TES. It is found that cooling TES value remains approximately constant as wind penetration increases, but generally decreases with increasing solar penetration. It is also clearly shown that the storage management strategy is vitally important to the economic value of TES; utility side operating methods perform with at least 75% greater value as compared to building side management strategies. In addition, TES compares fairly well against batteries, obtaining nearly 90% of the battery value in the base case; this result is significant considering TES can only impact building thermal loads, whereas batteries can impact any electrical load. Surprisingly, the value of energy storage does not increase substantially with increased wind and solar penetration and in some cases it decreases. This result is true for both TES and batteries and suggests that the tie between load shifting energy storage and renewable electric power generation may not be nearly as strong as typically thought.

Byron W. Jones; Robert Powell

2015-01-01T23:59:59.000Z

117

Environmental permits and approvals plan for high-level waste interim storage, Project W-464  

SciTech Connect

This report discusses the Permitting Plan regarding NEPA, SEPA, RCRA, and other regulatory standards and alternatives, for planning the environmental permitting of the Canister Storage Building, Project W-464.

Deffenbaugh, M.L.

1998-05-28T23:59:59.000Z

118

Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes  

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

1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] 1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes DOE/EIS-0212 VOLUME 1 OF 2 VOLUME 1 FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE OF HANFORD TANK WASTES Hanford Site Richland, Washington October, 1995 WASHINGTON STATE DEPARTMENT OF ECOLOGY NUCLEAR WASTE PROGRAM LACEY, WASHINGTON 98503 U.S. DEPARTMENT OF ENERGY RICHLAND OPERATIONS OFFICE

119

EIS-0212: Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, WA  

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

This environmental impact statement asseses Department of Energy and Washington State Department of Ecology maintanence of safe storage of high-level radioactive wastes currently stored in the older single-shell tanks, the Watchlist Tank 101-SY, and future waste volumes associated with tank farm and other Hanford facility operations, including a need to provide a modern safe, reliable, and regulatory-compliant replacement cross-site transfer capability. The purpose of this action is to prevent uncontrolled releases to the environment by maintaining safe storage of high-level tank wastes.

120

Structural analyses of the storage container for heavy element facility, building-251  

SciTech Connect

The Heavy Element Facility, Building 251, contains a series of underground storage vaults which are used for long term storage of nuclear materials. A storage rack with shelves is suspended from the top of each storage vault. The stainless steel containers enclosing the nuclear materials are stored on the shelves. A Hazard & Accident assessment analyzed the vulnerability of this storage system to assaults resulting from natural phenomena and accidents within the building. The assessment considered all racks and their containers to be stored underground and secured in their static, long-term configuration. Moving beyond the static, long-term hazard assessment, the structural analyses were performed to evaluate the storage container against a rare, short duration event. An accidental free drop of a container may occur in a combination of two events: a rare, short-duration earthquake concurrent with an operation of raising the storage rack to a maximum height that the crane is capable of. This hypothetical free drop may occur only to the container in the uppermost shelf of the storage rack. The analyses were the structural evaluation of the storage container to determine the material containment integrity of the storage container after the accident. The evaluation was performed simulating a free drop from the storage rack, with a maximum load in the container, striking/an unyielding surface in the worst orientation. The analyses revealed that, in the very unlikely event of a container drop, the integrity of the hermetic seal of the storage container could be compromised due to plastic deformation of the lid and mating flange. Simple engineering and administrative controls can prevent that from occurring.

Ng, D S

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

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

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada Test Site (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

122

BuildingDepot: An Extensible and Distributed Architecture for Building Data Storage, Access and Sharing  

E-Print Network (OSTI)

to devise intelligent data-driven methods for energy efficient use of building systems. Most current a prototype of BuildingDepot, along with connectors to several standard energy management systems, showing how Introduction Improving energy efficiency in buildings has emerged as an important societal issue and research

Gupta, Rajesh

123

Predictive Optimal Control of Active and Passive Building Thermal Storage Inventory  

SciTech Connect

Cooling of commercial buildings contributes significantly to the peak demand placed on an electrical utility grid. Time-of-use electricity rates encourage shifting of electrical loads to off-peak periods at night and weekends. Buildings can respond to these pricing signals by shifting cooling-related thermal loads either by precooling the building's massive structure or the use of active thermal energy storage systems such as ice storage. While these two thermal batteries have been engaged separately in the past, this project investigated the merits of harnessing both storage media concurrently in the context of predictive optimal control. To pursue the analysis, modeling, and simulation research of Phase 1, two separate simulation environments were developed. Based on the new dynamic building simulation program EnergyPlus, a utility rate module, two thermal energy storage models were added. Also, a sequential optimization approach to the cost minimization problem using direct search, gradient-based, and dynamic programming methods was incorporated. The objective function was the total utility bill including the cost of reheat and a time-of-use electricity rate either with or without demand charges. An alternative simulation environment based on TRNSYS and Matlab was developed to allow for comparison and cross-validation with EnergyPlus. The initial evaluation of the theoretical potential of the combined optimal control assumed perfect weather prediction and match between the building model and the actual building counterpart. The analysis showed that the combined utilization leads to cost savings that is significantly greater than either storage but less than the sum of the individual savings. The findings reveal that the cooling-related on-peak electrical demand of commercial buildings can be considerably reduced. A subsequent analysis of the impact of forecasting uncertainty in the required short-term weather forecasts determined that it takes only very simple short-term prediction models to realize almost all of the theoretical potential of this control strategy. Further work evaluated the impact of modeling accuracy on the model-based closed-loop predictive optimal controller to minimize utility cost. The following guidelines have been derived: For an internal heat gain dominated commercial building, reasonable geometry simplifications are acceptable without a loss of cost savings potential. In fact, zoning simplification may improve optimizer performance and save computation time. The mass of the internal structure did not show a strong effect on the optimization. Building construction characteristics were found to impact building passive thermal storage capacity. It is thus advisable to make sure the construction material is well modeled. Zone temperature setpoint profiles and TES performance are strongly affected by mismatches in internal heat gains, especially when they are underestimated. Since they are a key factor in determining the building cooling load, efforts should be made to keep the internal gain mismatch as small as possible. Efficiencies of the building energy systems affect both zone temperature setpoints and active TES operation because of the coupling of the base chiller for building precooling and the icemaking TES chiller. Relative efficiencies of the base and TES chillers will determine the balance of operation of the two chillers. The impact of mismatch in this category may be significant. Next, a parametric analysis was conducted to assess the effects of building mass, utility rate, building location and season, thermal comfort, central plant capacities, and an economizer on the cost saving performance of optimal control for active and passive building thermal storage inventory. The key findings are: (1) Heavy-mass buildings, strong-incentive time-of-use electrical utility rates, and large on-peak cooling loads will likely lead to attractive savings resulting from optimal combined thermal storage control. (2) By using economizer to take advantage of the cool fresh air during the night, the bu

Gregor P. Henze; Moncef Krarti

2005-09-30T23:59:59.000Z

124

Fire hazard analysis for the fuel supply shutdown storage buildings  

SciTech Connect

The purpose of a fire hazards analysis (FHA) is to comprehensively assess the risk from fire and other perils within individual fire areas in a DOE facility in relation to proposed fire protection so as to ascertain whether the objectives of DOE 5480.7A, Fire Protection, are met. This Fire Hazards Analysis was prepared as required by HNF-PRO-350, Fire Hazards Analysis Requirements, (Reference 7) for a portion of the 300 Area N Reactor Fuel Fabrication and Storage Facility.

REMAIZE, J.A.

2000-09-27T23:59:59.000Z

125

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

SciTech Connect

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1994-06-01T23:59:59.000Z

126

Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF...  

Open Energy Info (EERE)

Treatment, Storage and Disposal Facilities (TSDF) Guidance Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

127

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I. [Los Alamos Technical Associates, Inc., NM (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

128

Statement of position of the United States Department of Energy in the matter of proposed rulemaking on the storage and disposal of nuclear waste (waste confidence rulemaking)  

SciTech Connect

Purpose of this proceeding is to assess generically the degree of assurance that the radioactive waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to determine whether wastes can be safely stored on-site past license expiration until off-site disposal/storage is available. (DLC)

None

1980-04-15T23:59:59.000Z

129

Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB) Process Flow Diagram Mass Balance Calculations  

SciTech Connect

The purpose of these calculations is to develop the material balances for documentation of the Canister Storage Building (CSB) Process Flow Diagram (PFD) and future reference. The attached mass balances were prepared to support revision two of the PFD for the CSB. The calculations refer to diagram H-2-825869.

KLEM, M.J.

2000-05-11T23:59:59.000Z

130

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

131

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

132

Carbon Sequestration Kinetic and Storage Capacity of Ultramafic Mining Waste  

Science Journals Connector (OSTI)

Mineral carbonation of ultramafic rocks provides an environmentally safe and permanent solution for CO2 sequestration. In order to assess the carbonation potential of ultramafic waste material produced by industrial processing, we designed a laboratory-...

Julie Pronost; Georges Beaudoin; Joniel Tremblay; Faïçal Larachi; Josée Duchesne; Réjean Hébert; Marc Constantin

2011-09-15T23:59:59.000Z

133

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

134

Optimal design of ground source heat pump system integrated with phase change cooling storage tank in an office building  

E-Print Network (OSTI)

Optimal design of ground source heat pump system integrated with phase change cooling storage tank in an office building Na Zhu*, Yu Lei, Pingfang Hu, Linghong Xu, Zhangning Jiang Department of Building Environment and Equipment Engineering... heat pump system integrated with phase change cooling storage technology could save energy and shift peak load. This paper studied the optimal design of a ground source heat pump system integrated with phase change thermal storage tank in an office...

Zhu, N.

2014-01-01T23:59:59.000Z

135

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect

This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard.

FOWLER KD

2007-12-27T23:59:59.000Z

136

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect

The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.

WEBER RA

2009-01-16T23:59:59.000Z

137

Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program  

SciTech Connect

Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

Not Available

1986-05-01T23:59:59.000Z

138

Energy storage for desalination processes powered by renewable energy and waste heat sources  

Science Journals Connector (OSTI)

Abstract Desalination has become imperative as a drinking water source for many parts of the world. Due to the large quantities of thermal energy and high quality electricity requirements for water purification, the desalination industry depends on waste heat resources and renewable energy sources such as solar collectors, photovoltaic arrays, geothermal and wind and tidal energy sources. Considering the mismatch between the source supply and demand and intermittent nature of these energy resources, energy storage is a must for reliable and continuous operation of desalination facilities. Thermal energy storage (TES) requires a suitable medium for storage and circulation while the photovoltaic/wind generated electricity needs to be stored in batteries for later use. Desalination technologies that utilize thermal energy and thus require storage for uninterrupted process operation are multi-stage flash distillation (MSF), multi-effect evaporation (MED), low temperature desalination (LTD) and humidification–dehumidification (HD) and membrane distillation (MD). Energy accumulation, storage and supply are the key components of energy storage concept which improve process performance along with better resource economics, and minimum environmental impact. Similarly, the battery energy storage (BES) is essential to store electrical energy for electrodialysis (ED), reverse osmosis (RO) and mechanical vapor compression (MVC) technologies. This research-review paper provides a critical review on current energy storage options for different desalination processes powered by various renewable energy and waste heat sources with focus on thermal energy storage and battery energy storage systems. Principles of energy storage (thermal and electrical energy) are discussed with details on the design, sizing, and economics for desalination process applications.

Veera Gnaneswar Gude

2014-01-01T23:59:59.000Z

139

Thermoeconomic optimization of sensible heat thermal storage for cogenerated waste-to-energy recovery  

SciTech Connect

This paper investigates the feasibility of employing thermal storage for cogenerated waste-to-energy recovery such as using mass-burning water-wall incinerators and topping steam turbines. Sensible thermal storage is considered in rectangular cross-sectioned channels through which is passed unused process steam at 1,307 kPa/250 C (175 psig/482 F) during the storage period and feedwater at 1,307 kPa/102 C (175 psig/216 F) during the recovery period. In determining the optimum storage configuration, it is found that the economic feasibility is a function of mass and specific heat of the material and surface area of the channel as well as cost of material and fabrication. Economic considerations included typical cash flows of capital charges, energy revenues, operation and maintenance, and income taxes. Cast concrete is determined to be a potentially attractive storage medium.

Abdul-Razzak, H.A. [Texas A and M Univ., Kingsville, TX (United States). Dept. of Mechanical and Industrial Engineering; Porter, R.W. [Illinois Inst. of Tech., chicago, IL (United States). Dept. of Mechanical and Aerospace Engineering

1995-10-01T23:59:59.000Z

140

Cryograb: A Novel Approach to the Retrieval of Waste from Underground Storage Tanks - 13501  

SciTech Connect

The UK's National Nuclear Laboratory (NNL) is investigating the use of cryogenic technology for the recovery of nuclear waste. Cryograb, freezing the waste on a 'cryo-head' and then retrieves it as a single mass which can then be treated or stabilized as necessary. The technology has a number of benefits over other retrieval approaches in that it minimizes sludge disturbance thereby reducing effluent arising and it can be used to de-water, and thereby reduce the volume of waste. The technology has been successfully deployed for a variety of nuclear and non-nuclear waste recovery operations. The application of Cryograb for the recovery of waste from US underground storage tanks is being explored through a US DOE International Technology Transfer and Demonstration programme. A sample deployment being considered involves the recovery of residual mounds of sludge material from waste storage tanks at Savannah River. Operational constraints and success criteria were agreed prior to the completion of a process down selection exercise which specified the preferred configuration of the cryo-head and supporting plant. Subsequent process modeling identified retrieval rates and temperature gradients through the waste and tank infrastructure. The work, which has been delivered in partnership with US DOE, SRNL, NuVision Engineering and Frigeo AB has demonstrated the technical feasibility of the approach (to TRL 2) and has resulted in the allocation of additional funding from DOE to take the programme to bench and cold pilot-scale trials. (authors)

O'Brien, Luke; Baker, Stephen; Bowen, Bob [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom)] [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom); Mallick, Pramod; Smith, Gary [US Department of Energy (United States)] [US Department of Energy (United States); King, Bill [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Judd, Laurie [NuVision Engineering (United States)] [NuVision Engineering (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Thermal Energy Storage/Waste Heat Recovery Applications in the Cement Industry  

E-Print Network (OSTI)

, and the Portland Cement Association have studied the potential benefits of using waste heat recovery methods and thermal energy storage systems in the cement manufacturing process. This work was performed under DOE Contract No. EC-77-C-01-50S4. The study has been...

Beshore, D. G.; Jaeger, F. A.; Gartner, E. M.

1979-01-01T23:59:59.000Z

142

Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112  

SciTech Connect

This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities.

Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

1994-11-01T23:59:59.000Z

143

High-level waste canister storage final design, installation, and testing. Topical report  

SciTech Connect

This report is a description of the West Valley Demonstration Project`s radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project`s vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access.

Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

1998-04-01T23:59:59.000Z

144

Assessing health impacts of CO2 leakage from a geological storage site into buildings: role of attenuation in the unsaturated zone and building foundation  

E-Print Network (OSTI)

a) Title Assessing health impacts of CO2 leakage from a geological storage site into buildings of the greenhouse gas CO2 has the potential to be a widespread and effective option to mitigate climate change. As any industrial activity, CO2 storage may lead to adverse impact on human health and the environment

Paris-Sud XI, Université de

145

Comprehensive work plan for Building 3001 storage canal at the Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

This Comprehensive Work Plan describes the method of accomplishment to replace the shielding protection of the water in the canal with a controlled low strength material (CLSM) 4. The canal was used during the operation of the Oak Ridge Graphite Reactor in the 1940s and 1950s to transport spent fuel slugs and irradiated test materials from the reactor, under water to the hot cell in Building 3019 for further processing, packaging, and handling. After the reactor was shut down, the canal was used until 1990 to store some irradiated materials until they could be transferred to a Solid Waste Storage Area. This task has the following objectives and components: (1) minimize potential future risk to human health and the environment; (2) reduce surveillance and maintenance cost of the canal; (3) perform site preparation activities; (4) replace the water in the canal with a solid CLSM; (5) pump the water to the Process Waste Treatment System (PWTS) for further processing at the same rate that the CLSM is pumped under the water; (6) remove the water using a process that will protect the workers and the public in the visitors area from contamination while the CLSM is being pumped underneath the water; (7) painting a protective coating material over the CLSM after the CLSM has cured.

NONE

1997-01-01T23:59:59.000Z

146

A visual assessment of the concrete vaults which surround underground waste storage tanks  

SciTech Connect

Radioactive waste produced at the Savannah River Site (SRS) is stored in underground tanks. There are four different waste tank designs. For each waste tank design the outermost containment shield between the waste and the soil is a concrete vault surrounding the carbon steel liner(s). Should the primary and/or secondary liner be breached, the concrete vault would slow transport of the waste so that contamination of the soil is minimized. The type 3 waste tanks have a stated design life of 40--60 years. With the uncertainty of the schedule for transfer of the waste to the Defense Waste Processing Facility, it is conceivable that the tanks will be required to function past their design life. The Department of Energy formed a Waste Tank Structural Integrity Panel to investigate the potential for aging and degradation of underground radioactive waste storage tanks employed in the weapons complex. The panel is focusing on how each site in the complex: (1) inspects the waste tanks for degradation, (2) understands the potential degradation mechanisms which may occur at their sites, and (3) mitigates the known potential degradation mechanisms. In addition to the carbon steel liners, the degradation of the concrete vault has also been addressed by the panel. High Level Waste Engineering (HLWE) at SRS has formed a task team to identify key issues that determine and/or effect the condition of the concrete. In June 1993, slides were reviewed which showed the inside of the concrete vault in Type 1, 2, and 4 tanks. The authors subsequently visited the tank farm and assessed the visible portions of the outer concrete vault. Later a team of engineers knowledgeable in concrete degradation performed a walk-down. Photographs showing the concrete condition were taken at this time. This report summarizes the findings of these walk-downs and reinforces previous recommendations.

Wiersma, B.J.; Shurrab, M.S.

1993-12-01T23:59:59.000Z

147

Energy Analysis and Energy Conservation Options for the Addition to Records Storage Building  

E-Print Network (OSTI)

REPORT Submitted by Mohsen Farzad Dennis L. O'Neal Prepared For Energy Efficiency Division Texas Public Utility Commission Austin, Texas ABSTRACT The energy use and peak load requirements of the addition to Records Storage Building in Austin, Texas were... reflectivity and low overall heat transfer coefficient was used to study the reduction of glass conduction and glass solar loads. Other options which were studied included increasing the wall and roof insulation,- reducing the light level, temperature setback...

Farzad, M.; O'Neal, D. L.

1986-01-01T23:59:59.000Z

148

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-01-01T23:59:59.000Z

149

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-12-31T23:59:59.000Z

150

CSER 94-004: Criticality safety of double-shell waste storage tanks  

SciTech Connect

This criticality safety evaluation covers double-shell waste storage tanks (DSTs), double-contained receiver tanks (DCRTs), vault tanks, and the 242-A Evaporator located in the High Level Waste (HLW) Tank Farms on the Hanford Site. Limits and controls are specified and the basis for ensuring criticality safety is discussed. A minimum limit of 1,000 is placed upon the solids/plutonium mass ratio in incoming waste. The average solids/Pu mass ratio over all waste in tank farms is estimated to be about 74,500, about 150 times larger than required to assure subcriticality in homogeneous waste. PFP waste in Tank-102-SY has an estimated solids/Pu mass ratio of 10,000. Subcriticality is assured whenever the plutonium concentration is less than 2.6 g. The median reported plutonium concentration for 200 samples of waste solids is about 0.01 g (0.038 g/gal). A surveillance program is proposed to increase the knowledge of the waste and provide added assurance of the high degree of subcriticality.

Rogers, C.A.

1994-09-22T23:59:59.000Z

151

Design and Simulation for a Solar House with Building Integrated Photovoltaic-Thermal System and Thermal Storage  

Science Journals Connector (OSTI)

Building integrated photovoltaic-thermal systems (BIPV/T) that pre-heat ambient air may be used in combination with ventilated concrete slabs for thermal storage purposes. This is one of many feasible ways to ...

YuXiang Chen; A. K. Athienitis; K. E. Galal…

2009-01-01T23:59:59.000Z

152

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington  

SciTech Connect

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Not Available

1994-07-01T23:59:59.000Z

153

A Short History of Hanford Waste Generation, Storage, and Release  

SciTech Connect

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

Gephart, Roy E.

2003-10-01T23:59:59.000Z

154

WASTE SOLIDIFICATION BUILDING BENCH SCALE HIGH ACTIVITY WASTE SIMULANT VARIABILITY STUDY FY2008  

SciTech Connect

The primary objective of this task was to perform a variability study of the high activity waste (HAW) acidic feed to determine the impact of feed variability on the quality of the final grout and on the mixability of the salt solution into the dry powders. The HAW acidic feeds were processed through the neutralization/pH process, targeting a final pH of 12. These fluids were then blended with the dry materials to make the final waste forms. A secondary objective was to determine if elemental substitution for cost prohibitive or toxic elements in the simulant affects the mixing response, thus providing a more economical simulant for use in full scale tests. Though not an objective, the HAW simulant used in the full scale tests was also tested and compared to the results from this task. A statistically designed test matrix was developed based on the maximum molarity inputs used to make the acidic solutions. The maximum molarity inputs were: 7.39 HNO{sub 3}, 0.11618 gallium, 0.5423 silver, and 1.1032 'other' metals based on their NO{sub 3}{sup -} contribution. Substitution of the elements aluminum for gallium and copper for silver was also considered in this test matrix, resulting in a total of 40 tests. During the NaOH addition, the neutralization/pH adjustment process was controlled to a maximum temperature of 60 C. The neutralized/pH adjusted simulants were blended with Portland cement and zircon flour at a water to cement mass ratio of 0.30. The mass ratio of zircon flour to Portland cement was 1/12. The grout was made using a Hobart N-50 mixer running at low speed for two minutes to incorporate and properly wet the dry solids with liquid and at medium speed for five minutes for mixing. The resulting fresh grout was measured for three consecutive yield stress measurements. The cured grout was measured for set, bleed, and density. Given the conditions of preparing the grout in this task, all of the grouts were visually well mixed prior to preparing the grouts for measurements. All of the cured grouts were measured for bleed and set. All of the cured grouts satisfied the bleed and set requirements, where no bleed water was observed on any of the grout samples after one day and all had set within 3 days of curing. This data indicates, for a well mixed product, bleed and set requirement are satisfied for the range of acidic feeds tested in this task. The yield stress measurements provide both an indication on the mixability of the salt solution with dry materials and an indication of how quickly the grout is starting to form structure. The inability to properly mix these two streams into a well mixed grout product will lead to a non-homogeneous mixture that will impact product quality. Product quality issues could be unmixed regions of dry material and hot spots having high concentrations of americium 241. Mixes that were more difficult to incorporate typically resulted in grouts with higher yield stresses. The mixability from these tests will provide Waste Solidification Building (WSB) an indication of which grouts will be more challenging to mix. The first yield stress measurements were statistically compared to a list of variables, specifically the batched chemicals used to make the acidic solutions. The first yield stress was also compared to the physical properties of the acidic solutions, physical and pH properties of the neutralized/pH adjusted solutions, and chemical and physical properties of the grout.

Hansen, E; Timothy Jones, T; Tommy Edwards, T; Alex Cozzi, A

2009-03-20T23:59:59.000Z

155

A ground-coupled storage heat pump system with waste heat recovery  

SciTech Connect

This paper reports on an experimental single-family residence that was constructed to demonstrate integration of waste heat recovery and seasonal energy storage using both a ventilating and a ground-coupled heat pump. Called the Idaho energy Conservation Technology House, it combines superinsulated home construction with a ventilating hot water heater and a ground coupled water-to-water heat pump system. The ground heat exchangers are designed to economically promote seasonal and waste heat storage. Construction of the house was completed in the spring of 1989. Located in Moscow, Idaho, the house is occupied by a family of three. The 3,500 ft{sup 2} (325 m{sup 2}) two-story house combines several unique sub-systems that all interact to minimize energy consumption for space heating and cooling, and domestic hot water.

Drown, D.C.; Braven, K.R.D. (Univ. of Idaho, ID (US)); Kast, T.P. (Thermal Dynamic Towers, Boulder, CO (US))

1992-02-01T23:59:59.000Z

156

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1  

SciTech Connect

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14T23:59:59.000Z

157

Webinar: Make Your Building Sing!: Building-Retuning to Reduce Energy Waste  

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

Panelists: Eileen Gohr and Steve Harrison, Parameter Realty Partners; Dennis Bohlayer, Towson University; Benjamin Goldstein, U.S. Department of Energy; Lisa Shulock, Building Owners and Managers...

158

Long-term changes in nitrogen loads of a stream in the vicinity of an earthen waste storage pond  

Science Journals Connector (OSTI)

It is not sufficiently known for how long earthen waste storage ponds that are no more in use continue to affect surface water quality. In 2006, we carried out an investigation on the water quality and hydrolo...

T. Kato; H. Kuroda; H. Nakasone

2008-09-01T23:59:59.000Z

159

Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2  

SciTech Connect

This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P. [and others

1997-09-01T23:59:59.000Z

160

Canister storage building (CSB) safety analysis report phase 3: Safety analysis documentation supporting CSB construction  

SciTech Connect

The Canister Storage Building (CSB) will be constructed in the 200 East Area of the U.S. Department of Energy (DOE) Hanford Site. The CSB will be used to stage and store spent nuclear fuel (SNF) removed from the Hanford Site K Basins. The objective of this chapter is to describe the characteristics of the site on which the CSB will be located. This description will support the hazard analysis and accident analyses in Chapter 3.0. The purpose of this report is to provide an evaluation of the CSB design criteria, the design's compliance with the applicable criteria, and the basis for authorization to proceed with construction of the CSB.

Garvin, L.J.

1997-04-28T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

System Configuration Management Implementation Procedure for the Canister Storage Building (CSB)  

SciTech Connect

This document provides configuration management for the Distributed Control System (DCS), the Gaseous Effluent Monitoring System (GEMS-100) System, the Heating Ventilation and Air Conditioning (HVAC) Programmable Logic Controller (PLC), the Canister Receiving Crane (CRC) CRN-001 PLC, and both North and South vestibule door interlock system PLCs at the Canister Storage Building (CSB). This procedure identifies and defines software configuration items in the CSB control and monitoring systems, and defines configuration control throughout the system life cycle. Components of this control include: configuration status accounting; physical protection and control; and verification of the completeness and correctness of these items.

GARRISON, R.C.

2000-11-28T23:59:59.000Z

162

EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site  

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

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on-site, and two off-site management alternatives.

163

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6  

SciTech Connect

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

Not Available

1994-04-01T23:59:59.000Z

164

Final Environmental Impact Statement (Supplement to ERDA-1537, September 1977) Waste Management Operations Double-Shell Tanks for Defense High-Level Radioactive Waste Storage Savannah River Plant  

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

Do Do E/EIS-0062 FINAL ENVIRONMENTAL IMPACT mATEIUIENT (Supplement to ERDA-1537, September 1977) Waste ~ Management Operations Savannah River Plant ! Aiken, South Carolina Double-Shell Tanks for Defense High-Level Radioactive Waste Storage April 1980 U.S. DEPARTMENT OF ENERGY WASHINGTON. D.C.20545 1980 WL 94273 (F.R.) NOTICES DEPARTMENT OF ENERGY Office of Deputy Assistant Secretary for Nuclear Waste Management Double-Shell Tanks for Defense High-Level Radioactive Waste Storage, Savannah River Plant, Aiken, S.C. Wednesday, July 9, 1980 *46154 Record of Decision Decision. The decision has been made to complete the construction of the 14 double-shell tanks and use them to store defense high-level radioactive waste at the Savannah River Plant (SRP). Background. The SRP, located near Aiken, South Carolina, is a major installation of the

165

EIS-0062: Double-Shell Tanks for Defense High Level Waste Storage, Savannah River Site, Aiken, SC  

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

This EIS analyzes the impacts of the various design alternatives for the construction of fourteen 1.3 million gallon high-activity radioactive waste tanks. The EIS further evaluates the effects of these alternative designs on tank durability, on the ease of waste retrieval from such tanks, and the choice of technology and timing for long-term storage or disposal of the wastes.

166

US Department of Energy Storage of Spent Fuel and High Level Waste  

SciTech Connect

ABSTRACT This paper provides an overview of the Department of Energy's (DOE) spent nuclear fuel (SNF) and high level waste (HLW) storage management. Like commercial reactor fuel, DOE's SNF and HLW were destined for the Yucca Mountain repository. In March 2010, the DOE filed a motion with the Nuclear Regulatory Commission (NRC) to withdraw the license application for the repository at Yucca Mountain. A new repository is now decades away. The default for the commercial and DOE research reactor fuel and HLW is on-site storage for the foreseeable future. Though the motion to withdraw the license application and delay opening of a repository signals extended storage, DOE's immediate plans for management of its SNF and HLW remain the same as before Yucca Mountain was designated as the repository, though it has expanded its research and development efforts to ensure safe extended storage. This paper outlines some of the proposed research that DOE is conducting and will use to enhance its storage systems and facilities.

Sandra M Birk

2010-10-01T23:59:59.000Z

167

Nuclear Waste Repository Plan Approved by Senate  

Science Journals Connector (OSTI)

Bill calls for selection of permanent repository site by 1989, building of a retrievable waste facility, cash payments states with storage sites ... After considerable debate, the Senate has approved a plan aimed at getting the federal government's effort to find a long-term storage site for spent nuclear fuel and highlevel nuclear wastes off dead center and out of the political crossfire. ...

JANICE LONG

1987-12-07T23:59:59.000Z

168

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

and solar thermal collectors; electrical storage, flowis disallowed; 5. a low storage, PV, and solar thermal priceand heat storage; heat exchangers for application of solar

Stadler, Michael

2008-01-01T23:59:59.000Z

169

Ion implantation effects in insulators and the long-term stability of radioactive waste storage materials  

Science Journals Connector (OSTI)

Most insulator materials so far proposed for storing high-level radioactive wastes, such as glass and and the constituent minerals of ceramics are nuclear track detectors. Lead ion implantation experiments show that such materials should be transformed into “giant” nuclear tracks, when the internal fluence of heavy recoils emitted during the ?-decay of actinide elements stored in them exceeds a critical value, which corresponds to an equivalent storage period of a few thousand years for the wastes expected from a pressurized water reactor. In contrast, actinide bearing minerals are much more stable against ?-recoil damage. As nuclear tracks are extremely chemical reactive, ?-recoil damage is expected to shorten the lifetime of storage materials such as glass and ceramics against dissolution in ground waters. Fortunately new nuclear track concepts are already yielding guidelines for predicting and improving the long-term stability of storage materials. The results of the present studies also bear on the physics of ion implantation phenomena an insulator targets exposed to high fluences of low energy ions.

J.C. Dran; Y. Langevin; M. Maurette; J.C. Petit; B. Vassent

1981-01-01T23:59:59.000Z

170

Equipment design guidance document for flammable gas waste storage tank new equipment  

SciTech Connect

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas.

Smet, D.B.

1996-04-11T23:59:59.000Z

171

DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary  

SciTech Connect

This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis.

DeMuth, S.F.

1996-10-01T23:59:59.000Z

172

A Phase Change Storage Material that May be Used in the Fire Resistance of Building Structure  

Science Journals Connector (OSTI)

Abstract This study prepared polyethylene glycol/silicon dioxide composite, a kind of form-stable phase change material. The composites can be made into mortar which is able to adhere to the surface of building structure and absorb the fire heat. This paper aims to study the effect of the composites on the fire resistance of building structure. Scanning electronic microscope and differential scanning calorimeter were adopted to investigate the structural and thermal properties of the composites. It was found that the polyethylene glycol was well dispersed into the network of solid SiO2. And the latent heat of PEG/SiO2 increased with the decrease of SiO2 content. The required weight percentage of SiO2 was found to be 15% at least if the composites remain solid without leakage. It was also found that a phase change of pure PEG6000 happened with an enthalpy of 158 J/g while the 80 wt% PEG composite is 133 J/g. In conclusion, the phase change storage material may be used for fire resistance of building structure.

Peng Wang; Na Li; Cheng-shou Zhao; Liu-yan Wu; Guo-bin Han

2014-01-01T23:59:59.000Z

173

The Technical and Economical Analysis of a Centralized Air-Conditioning System with Cold Storage Refrigeration in High-Rise Residential Buildings  

E-Print Network (OSTI)

In recent years, the application of a centralized air-conditioning system (CACS) with cold storage refrigeration in high-rise residential buildings has gradually increased. Due to the large difference between civil residential buildings...

Xiang, C.; Xie, G.

2006-01-01T23:59:59.000Z

174

Title: An Advanced Solution for the Storage, Transportation and Disposal of Vitrified High Level Waste  

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

Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 1 AN ADVANCED SOLUTION FOR THE STORAGE, TRANSPORTATION AND DISPOSAL OF SPENT FUEL AND VITRIFIED HIGH LEVEL WASTE William J. Quapp Teton Technologies, Inc. 860 W. Riverview Dr. Idaho Falls, ID 83401 208-535-9001 ABSTRACT For future nuclear power deployment in the US, certain changes in the back end of the fuel cycle, i.e., disposal of high level waste and spent fuel, must become a real options. However, there exists another problem from the front end of the fuel cycle which has until recently, received less attention. Depleted uranium hexafluoride is a by-product of the enrichment process and has accumulated for over 50 years. It now represents a potential environmental problem. This paper describes a

175

Assessing the Feasibility of Interrogating Nuclear Waste Storage Silos using Cosmic-ray Muons  

E-Print Network (OSTI)

Muon radiography is a fast growing field in applied scientific research. In recent years, many detector technologies and imaging techniques using the Coulomb scattering and absorption properties of cosmic-ray muons have been developed for the non-destructive assay of various structures across a wide range of applications. This work presents the first results that assess the feasibility of using muons to interrogate waste silos within the UK Nuclear Industry. Two such approaches, using different techniques that exploit each of these properties, have previously been published, and show promising results from both simulation and experimental data for the detection of shielded high-Z materials and density variations from volcanic assay. Both detector systems are based on scintillator and photomultiplier technologies. Results from dedicated simulation studies using both these technologies and image reconstruction techniques are presented for an intermediate-sized nuclear waste storage facility filled with concrete...

Ambrosino, F; Cimmino, L; D'Alessandro, R; Ireland, D G; Kaiser, R; Mahon, D F; Mori, N; Noli, P; Saracino, G; Shearer, C; Viliani, L; Yang, G

2014-01-01T23:59:59.000Z

176

Radiolytic effects on ion exchangers during the storage of radioactive wastes  

SciTech Connect

Radiolytic effects on ion exchangers are being recognized as a significant problem in the processing and storage of high-specific-activity radioactive waste forms. Two major literature surveys and a series of scoping experiments conducted during this investigation indicate that radiation decomposition of ion exchange materials has the potential for a variety of undesirable consequences. These include the ready dispersion of adsorbed radionuclides to the environment, corrosion and pressurization of waste canisters, and generation of flammable and explosive gases, as well as agglomeration of ion exchangers to a rigid monolith with the partitioning of a liquid phase. Some of the highlights of the literature surveys and the major findings of the experimental studies are reported here.

Pillay, K.K.S.; Palau, G.L.

1982-01-01T23:59:59.000Z

177

Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations  

SciTech Connect

This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

1996-12-01T23:59:59.000Z

178

Seismic Vulnerability Assessment Waste Characterization Reduction and Repackaging Building, TA-50-69  

SciTech Connect

This report presents the results of the seismic structural analyses completed on the Waste Characterization Reduction and Repackaging (WCRR) Building in support of ongoing safety analyses. WCRR is designated as TA-50-69 at Los Alamos National Laboratory, Los Alamos, New Mexico. The facility has been evaluated against Department of Energy (DOE) seismic criteria for Natural Phenomena Hazards (NPH) Performance Category II (PC 2). The seismic capacities of two subsystems within the WCRR building, the material handling glove box and the lift rack immediately adjacent to the Glove Box are also documented, and the results are presented.

M.W.Sullivan; J.Ruminer; I.Cuesta

2003-02-02T23:59:59.000Z

179

ADMINISTRATIVE AND ENGINEERING CONTROLS FOR THE OPERATION OF VENTILATION SYSTEMS FOR UNDERGROUND RADIOACTIVE WASTE STORAGE TANKS  

SciTech Connect

Liquid radioactive wastes from the Savannah River Site are stored in large underground carbon steel tanks. The majority of the waste is confined in double shell tanks, which have a primary shell, where the waste is stored, and a secondary shell, which creates an annular region between the two shells, that provides secondary containment and leak detection capabilities should leakage from the primary shell occur. Each of the DST is equipped with a purge ventilation system for the interior of the primary shell and annulus ventilation system for the secondary containment. Administrative flammability controls require continuous ventilation to remove hydrogen gas and other vapors from the waste tanks while preventing the release of radionuclides to the atmosphere. Should a leak from the primary to the annulus occur, the annulus ventilation would also serve this purpose. The functionality of the annulus ventilation is necessary to preserve the structural integrity of the primary shell and the secondary. An administrative corrosion control program is in place to ensure integrity of the tank. Given the critical functions of the purge and annulus ventilation systems, engineering controls are also necessary to ensure that the systems remain robust. The system consists of components that are constructed of metal (e.g., steel, stainless steel, aluminum, copper, etc.) and/or polymeric (polypropylene, polyethylene, silicone, polyurethane, etc.) materials. The performance of these materials in anticipated service environments (e.g., normal waste storage, waste removal, etc.) was evaluated. The most aggressive vapor space environment occurs during chemical cleaning of the residual heels by utilizing oxalic acid. The presence of NO{sub x} and mercury in the vapors generated from the process could potentially accelerate the degradation of aluminum, carbon steel, and copper. Once identified, the most susceptible materials were either replaced and/or plans for discontinuing operations are executed.

Wiersma, B.; Hansen, A.

2013-11-13T23:59:59.000Z

180

Storage  

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

Storage Storage DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Storage A discussion of depleted UF6 cylinder storage activities and associated risks. Management Activities for Cylinders in Storage The long-term management of the existing DUF6 storage cylinders and the continual effort to remediate and maintain the safe condition of the DUF6 storage cylinders will remain a Departmental responsibility for many years into the future. The day to day management of the DUF6 cylinders includes actions designed to cost effectively maintain and improve their storage conditions, such as: General storage cylinder and storage yard maintenance; Performing regular inspections of cylinders; Restacking and respacing the cylinders to improve drainage and to

Note: This page contains sample records for the topic "waste storage building" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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181

Storage  

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

Environmental Risks » Storage Environmental Risks » Storage Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Storage Discussion of the potential environmental impacts from storage of depleted UF6 at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts Analyzed in the PEIS The PEIS included an analysis of the potential environmental impacts from continuing to store depleted UF6 cylinders at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts from Continued Storage of UF6 Cylinders Continued storage of the UF6 cylinders would require extending the use of a

182

Assessment of degradation concerns for spent fuel, high-level wastes, and transuranic wastes in monitored retrievalbe storage  

SciTech Connect

It has been concluded that there are no significant degradation mechanisms that could prevent the design, construction, and safe operation of monitored retrievable storage (MRS) facilities. However, there are some long-term degradation mechanisms that could affect the ability to maintain or readily retrieve spent fuel (SF), high-level wastes (HLW), and transuranic wastes (TRUW) several decades after emplacement. Although catastrophic failures are not anticipated, long-term degradation mechanisms have been identified that could, under certain conditions, cause failure of the SF cladding and/or failure of TRUW storage containers. Stress rupture limits for Zircaloy-clad SF in MRS range from 300 to 440/sup 0/C, based on limited data. Additional tests on irradiated Zircaloy (3- to 5-year duration) are needed to narrow this uncertainty. Cladding defect sizes could increase in air as a result of fuel density decreases due to oxidation. Oxidation tests (3- to 5-year duration) on SF are also needed to verify oxidation rates in air and to determine temperatures below which monitoring of an inert cover gas would not be required. Few, if any, changes in the physical state of HLW glass or canisters or their performance would occur under projected MRS conditions. The major uncertainty for HLW is in the heat transfer through cracked glass and glass devitrification above 500/sup 0/C. Additional study of TRUW is required. Some fraction of present TRUW containers would probably fail within the first 100 years of MRS, and some TRUW would be highly degraded upon retrieval, even in unfailed containers. One possible solution is the design of a 100-year container. 93 references, 28 figures, 17 tables.

Guenther, R.J.; Gilbert, E.R.; Slate, S.C.; Partain, W.L.; Divine, J.R.; Kreid, D.K.

1984-01-01T23:59:59.000Z

183

A facility design for repackaging ORNL CH-TRU legacy waste in Building 3525  

SciTech Connect

For the last 25 years, the Oak Ridge National Laboratory (ORNL) has conducted operations which have generated solid, contact-handled transuranic (CH-TRU) waste. At present the CH-TRU waste inventory at ORNL is about 3400 55-gal drums retrievably stored in RCRA-permitted, aboveground facilities. Of the 3400 drums, approximately 2600 drums will need to be repackaged. The current US Department of Energy (DOE) strategy for disposal of these drums is to transport them to the Waste Isolation Pilot Plant (WIPP) in New Mexico which only accepts TRU waste that meets a very specific set of criteria documented in the WIPP-WAC (waste acceptance criteria). This report describes activities that were performed from January 1994 to May 1995 associated with the design and preparation of an existing facility for repackaging and certifying some or all of the CH-TRU drums at ORNL to meet the WIPP-WAC. For this study, the Irradiated Fuel Examination Laboratory (IFEL) in Building 3525 was selected as the reference facility for modification. These design activities were terminated in May 1995 as more attractive options for CH-TRU waste repackaging were considered to be available. As a result, this document serves as a final report of those design activities.

Huxford, T.J.; Cooper, R.H. Jr.; Davis, L.E.; Fuller, A.B.; Gabbard, W.A.; Smith, R.B. [Oak Ridge National Lab., TN (United States); Guay, K.P. [S. M. Stroller Corp. (United States); Smith, L.C. [United Energy Services Corp. (United States)

1995-07-01T23:59:59.000Z

184

Envirocon to build plant for bioconversion of forestry wastes to animal feeds  

SciTech Connect

Envirocon Ltd. of Vancouver will build a pilot plant in British Columbia to produce protein supplement for animal feeds, making use of a biotechnological process patented by the University of Waterloo. When commerical viability has been proven, Envirocon will make use of the process in plants which it plans to design, manufacture, and install on a turnkey basis to convert waste from the pulp and paper industry to protein feed supplement.

Not Available

1982-04-01T23:59:59.000Z

185

Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)  

SciTech Connect

The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

COVEY, L.I.

2000-11-28T23:59:59.000Z

186

Degradation of transuranic waste drums in underground storage at the Hanford Site  

SciTech Connect

In situ inspections were performed on tarp-covered 55-gallon drums of transuranic (TRU) waste stored underground at the Hanford Site. These inspections were part of a task to characterize TRU drums for extent of corrosion degradation and uncertainty in TRU designation (inaccuracy in earlier assay determinations may have led to drums that actually were low-level waste to be termed TRU), and to attempt to correlate accuracy of existing records with actual drum contents. Two separate storage trench sites were investigated; a total of 90 drums were inspected with ultrasonic techniques and 104 additional drums were visually inspected. A high-humidity environment in the underground storage trenches had been reported in earlier investigations and was expected to result in substantial corrosion degradation. However, corrosion was much less than expected. Only a small percentage of drums had significant corrosion (with one breach) and the maximum rate was estimated at 0.051 mm/yr (2 mils/yr). The corrosion time of underground exposure was 14 to 15 years. These inspection results should be applicable to other similar environments (this applicability should be restricted to arid climates such as the Hanford Site) where drums are stored underground but shielded from direct soil contact by a tarp or other means. Soil contact would lead to more rapid corrosion.

Duncan, D.R.

1996-05-07T23:59:59.000Z

187

Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA  

SciTech Connect

Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

Dean, L.N. [Advanced Sciences, Inc., (United States)

1994-02-01T23:59:59.000Z

188

Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory  

SciTech Connect

This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L).

Ashwood, T.L.; Marsh, J.D. Jr.

1994-04-01T23:59:59.000Z

189

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

lead/acid battery, and thermal storage, capabilities, withhour electrical flow battery 8 thermal Not all constraintslifetime ( a) thermal storage 11 flow battery absorption

Stadler, Michael

2008-01-01T23:59:59.000Z

190

Development of Waste Acceptance Criteria at 221-U Building: Initial Flow and Transport Scoping Calculations  

SciTech Connect

This report documents numerical flow and transport simulations performed that establish initial waste acceptance criteria for the potential waste streams that may be safely sequestered in the 221-U Building and similar canyon structures. Specifically, simulations were executed to identify the maximum loading of contaminant mass (without respect to volume) that can be emplaced within the 221-U Building with no more than 1 pCi/m2 of contaminant migrating outside the structure within a 1,000 year time period. The initial scoping simulations were executed in one dimension to assess important processes, and then two dimensions to establish waste acceptance criteria. Two monolithic conditions were assessed: (1) a grouted canyon monolith; and (2) a canyon monolith filled with sand, both assuming no cracks or fissures were present to cause preferential transport. A three-staged approach was taken to account for different processes that may impact the amount of contaminant that can be safely sequestered in canyon structure. In the first stage, flow and transport simulations established waste acceptance criteria based on a linear (Kd) isotherm approach. In the second stage, impacts on thermal loading were examined and the differences in waste acceptance criteria quantified. In the third stage of modeling, precipitation/dissolution reactions were considered on the release and transport of the contaminants, and the subsequent impact on the maximum contaminant loading. The reactive transport modeling is considered a demonstration of the reactive transport capability, and shows the importance of its use for future performance predictions once site-specific data have been obtained.

Freedman, Vicky L.; Zhang, Z. F.; Keller, Jason M.; Chen, Yousu

2007-05-30T23:59:59.000Z

191

Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program  

SciTech Connect

This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

Not Available

1993-12-01T23:59:59.000Z

192

Update Direct-Strike Lightning Environment for Stockpile-to-Target Sequence: Supplement LLNL Subcontract #B568621 Lightning Protection at the Yucca Mountain Waste Storage Facility  

SciTech Connect

The University of Florida has surveyed all relevant publications reporting lightning damage to metals, metals which could be used as components of storage containers for nuclear waste materials. We show that even the most severe lightning could not penetrate the stainless steel thicknesses proposed for nuclear waste storage casks.

Uman, M A

2008-10-09T23:59:59.000Z

193

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

194

Building waste management core indicators through Spatial Material Flow Analysis: Net recovery and transport intensity indexes  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Sustainability and proximity principles have a key role in waste management. Black-Right-Pointing-Pointer Core indicators are needed in order to quantify and evaluate them. Black-Right-Pointing-Pointer A systematic, step-by-step approach is developed in this study for their development. Black-Right-Pointing-Pointer Transport may play a significant role in terms of environmental and economic costs. Black-Right-Pointing-Pointer Policy action is required in order to advance in the consecution of these principles. - Abstract: In this paper, the material and spatial characterization of the flows within a municipal solid waste (MSW) management system are combined through a Network-Based Spatial Material Flow Analysis. Using this information, two core indicators are developed for the bio-waste fraction, the Net Recovery Index (NRI) and the Transport Intensity Index (TII), which are aimed at assessing progress towards policy-related sustainable MSW management strategies and objectives. The NRI approaches the capacity of a MSW management system for converting waste into resources through a systematic metabolic approach, whereas the TII addresses efficiency in terms of the transport requirements to manage a specific waste flow throughout the entire MSW management life cycle. Therefore, both indicators could be useful in assessing key MSW management policy strategies, such as the consecution of higher recycling levels (sustainability principle) or the minimization of transport by locating treatment facilities closer to generation sources (proximity principle). To apply this methodological approach, the bio-waste management system of the region of Catalonia (Spain) has been chosen as a case study. Results show the adequacy of both indicators for identifying those points within the system with higher capacity to compromise its environmental, economic and social performance and therefore establishing clear targets for policy prioritization. Moreover, this methodological approach permits scenario building, which could be useful in assessing the outcomes of hypothetical scenarios, thus proving its adequacy for strategic planning.

Font Vivanco, David, E-mail: font@cml.leidenuniv.nl [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain); Institute of Environmental Sciences (CML), Leiden University, P.O. Box 9518, 2300 RA Leiden (Netherlands); Puig Ventosa, Ignasi [ENT Environment and Management, Carrer Sant Joan 39, First Floor, 08800 Vilanova i la Geltru, Barcelona (Spain); Gabarrell Durany, Xavier [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain)

2012-12-15T23:59:59.000Z

195

High dose radiolysis of aqueous solutions of chloromethanes: Importance in the storage of radioactive organic wastes  

Science Journals Connector (OSTI)

The radiolysis of aqueous solutions of chloromethanes (dichloromethane, CH2Cl2; chloroform, CHCl3; and carbon tetrachloride, CCl4) was performed with ?-rays to doses sufficient to completely decompose the solute in order to estimate the effects of radiation on the long-term storage of mixed waste in enclosed containers. One of the main relevant products was the inorganic chloride anion, which increased in concentration with increasing radiation dose due to the reactions of radiolytic decomposition products of water with the chloromethane. The pH of the solutions was observed to decrease with irradiation due to the formation of H3O+ as the counter ion to Cl?, i.e. the main radiolytic decomposition product is hydrochloric acid. Polymer formation was observed in aerated solutions as a precipitate while deaerated solutions exhibited a slight turbidity.

P. Rajesh; J.A. LaVerne; S.M. Pimblott

2007-01-01T23:59:59.000Z

196

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4  

SciTech Connect

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

Not Available

1994-04-01T23:59:59.000Z

197

Used Oil and Filter Disposal Used Oil: Create a segregated storage area or container. Label the container "Waste Oil Only".  

E-Print Network (OSTI)

Used Oil and Filter Disposal Used Oil: Create a segregated storage area or container. Label the container "Waste Oil Only". Maintain a written log to document all amounts and types of oil added to the container. No solvents, oil contaminated with solvents, PCBs, non-petroleum based oils, or any other

Maroncelli, Mark

198

Generation, storage, collection and transportation of municipal solid waste - A case study in the city of Kathmandu, capital of Nepal  

SciTech Connect

Solid waste management (SWM) services have consistently failed to keep up with the vast amount of solid waste produced in urban areas. There is not currently an efficient system in place for the management, storage, collection, and transportation of solid waste. Kathmandu City, an important urban center of South Asia, is no exception. In Kathmandu Metropolitan City, solid waste generation is predicted to be 1091 m{sup 3}/d (245 tons/day) and 1155 m{sup 3}/d (260 tons/day) for the years 2005 and 2006, respectively. The majority (89%) of households in Kathmandu Metropolitan City are willing to segregate the organic and non-organic portions of their waste. Overall collection efficiency was 94% in 2003. An increase in waste collection occurred due to private sector involvement, the shutdown of the second transfer station near the airport due to local protest, a lack of funding to maintain trucks/equipment, a huge increase in plastic waste, and the willingness of people to separate their waste into separate bins. Despite a substantial increase in total expenditure, no additional investments were made to the existing development plan to introduce a modern disposal system due to insufficient funding. Due to the lack of a proper lining, raw solid waste from the existing dumping site comes in contact with river water directly, causing severe river contamination and deteriorating the quality of the water.

Alam, R. [Shahjalal University of Science and Technology, Department of Civil and Environmental Engineering, Sylhet 3114 (Bangladesh)], E-mail: rakib_env@yahoo.com; Chowdhury, M.A.I.; Hasan, G.M.J.; Karanjit, B.; Shrestha, L.R. [Shahjalal University of Science and Technology, Department of Civil and Environmental Engineering, Sylhet 3114 (Bangladesh)

2008-07-01T23:59:59.000Z

199

THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP  

E-Print Network (OSTI)

F. J. Molz. Subsurface Waste Heat Storage, Experimentalfor land disposal of waste heat and waste water. Inst. forfor land disposal of waste heat and waste water. Inst. for

Authors, Various

2011-01-01T23:59:59.000Z

200

The National Building Competition: Working Off the Waste with ENERGY STAR  

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

0 COMPETITION SUMMARY 0 COMPETITION SUMMARY 2 On April 27, 2010, EPA launched the first-ever Na- tional Building Competition. Teams from fourteen buildings of all shapes and sizes located around the country went head to head to see who could work off the waste with help from EPA's ENERGY STAR pro- gram and reduce their energy use the most. The teams faced numerous challenges, including equipment malfunctions, staff departures, extreme temperatures, and tight budgets. In the face of these challenges, the competitors demonstrated that a strategic approach to energy efficiency can help orga- nizations overcome obstacles and achieve sustained, lasting improvement. Together, the contestants reduced their energy con- sumption by more than 44 million KBtu a year, saved more than $950,000, and reduced greenhouse gas

Note: This page contains sample records for the topic "waste storage building" 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

Design and operation methodology for active building-integrated thermal energy storage systems  

Science Journals Connector (OSTI)

Abstract A methodology is presented for integrating the design and operation of active building-integrated thermal energy storage (BITES) systems to enhance their thermal and energy performance. A bounding-condition based design approach is proposed in conjunction with predictive control strategies. The predictive control uses frequency domain models and room air temperature set-point profile as input. The set-point profiles and BITES design are improved in a holistic manner according to the thermal dynamic response of active BITES systems and their thermal zones. The dynamic response is obtained from the transfer functions of frequency domain models. The methodology is demonstrated on ventilated systems. The results show that the methodology can significantly improve the design and operation of active BITES systems, and hence improve their thermal and energy performance. The dynamic response of different sizes of systems is presented to provide useful information for design selection. It is shown that concrete thickness of 0.2–0.3 m is a good value to initiate design. Other important application considerations are also discussed.

Yuxiang Chen; Khaled E. Galal; Andreas K. Athienitis

2014-01-01T23:59:59.000Z

202

Human Factors Engineering and Ergonomics Analysis for the Canister Storage Building (CSB) Results and Findings  

SciTech Connect

The purpose for this supplemental report is to follow-up and update the information in SNF-3907, Human Factors Engineering (HFE) Analysis: Results and Findings. This supplemental report responds to applicable U.S. Department of Energy Safety Analysis Report review team comments and questions. This Human Factors Engineering and Ergonomics (HFE/Erg) analysis was conducted from April 1999 to July 1999; SNF-3907 was based on analyses accomplished in October 1998. The HFE/Erg findings presented in this report and SNF-3907, along with the results of HNF-3553, Spent Nuclear Fuel Project, Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report,'' Chapter A3.0, ''Hazards and Accidents Analyses,'' provide the technical basis for preparing or updating HNF-3553. Annex A, Chaptex A13.0, ''Human Factors Engineering.'' The findings presented in this report allow the HNF-3553 Chapter 13.0, ''Human Factors,'' to respond fully to the HFE requirements established in DOE Order 5480.23, Nuclear Safety Analysis Reports.

GARVIN, L.J.

1999-09-20T23:59:59.000Z

203

Functional and operational requirements document : building 1012, Battery and Energy Storage Device Test Facility, Sandia National Laboratories, New Mexico.  

SciTech Connect

This report provides an overview of information, prior studies, and analyses relevant to the development of functional and operational requirements for electrochemical testing of batteries and energy storage devices carried out by Sandia Organization 2546, Advanced Power Sources R&D. Electrochemical operations for this group are scheduled to transition from Sandia Building 894 to a new Building located in Sandia TA-II referred to as Building 1012. This report also provides background on select design considerations and identifies the Safety Goals, Stakeholder Objectives, and Design Objectives required by the Sandia Design Team to develop the Performance Criteria necessary to the design of Building 1012. This document recognizes the Architecture-Engineering (A-E) Team as the primary design entity. Where safety considerations are identified, suggestions are provided to provide context for the corresponding operational requirement(s).

Johns, William H.

2013-11-01T23:59:59.000Z

204

Submergible barge retrievable storage and permanent disposal system for radioactive waste  

DOE Patents (OSTI)

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

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

1981-01-01T23:59:59.000Z

205

TWRS retrieval and disposal mission, immobilized high-level waste storage plan  

SciTech Connect

This project plan has a two fold purpose. First, it provides a plan specific to the Hanford Tank Waste Remediation System (TWRS) Immobilized High-Level Waste (EMW) Storage Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestone M-90-01 (Ecology et al. 1996) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan. Second, it provides an upper tier document that can be used as the basis for future subproject line item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 (DOE 1992a) and 430.1 (DOE 1995)). The format and content of this project plan are designed to accommodate the plan`s dual purpose. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

Calmus, R.B.

1998-01-07T23:59:59.000Z

206

Imaging and Characterizing the Waste Materials Inside an Underground Storage Tank Using Seismic Normal Modes  

SciTech Connect

It is necessary to know something about the nature of the wastes in a Hanford underground storage tank (UST) so that the correct hardware can be inserted into a tank for sampling, sluicing, or pumping operations. It is also important to know if a layer of gas exists beneath solid and liquid layers of waste. Given that the tank will have only one liquid observation well (LOW), the authors examined the information that could be obtained from the natural seismic vibrations of a tank as a whole; that is, the normal modes of that tank. As in the case of a bell, the natural vibration, or normal modes, of a tank depend on many things, including the construction of the tank, the kinds of waste materials in the tank, the amount of each material in the tank, and where the energy is placed that excites the vibrations (i.e., where you will ''hit'' the tank). The nature of a normal mode of vibration can be given by its frequency and amplitude. For any given frequency, the amplitude of vibration can be given as a function of position in and around the tank. Since they assumed that one would be ''listening'' to a tank from locations along a LOW, they show their computed amplitudes as a function of position inside and around the tank, and in the case of the physical models they display the observations along various lines inside the tank model. This allowed us to see the complex geometry of each mode of oscillation as a function of increasing frequency.

M. N. Toksoz; R. M. Turpening

1999-09-14T23:59:59.000Z

207

Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site  

SciTech Connect

This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7).

Bohrman, D.E.; Ingram, E.M. [Oak Ridge Y-12 Plant, TN (United States)

1993-09-01T23:59:59.000Z

208

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies  

E-Print Network (OSTI)

efficiency requirements - Maximum emission limits Investment constraints: - Payback period is constrained Storage constraints: - Electricity stored is limited by battery

Stadler, Michael

2008-01-01T23:59:59.000Z

209

Mr. John E. Kieling, Chief Hazardous Waste Bureau  

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

Fe, NM 87508-6303 Subject: Notification of the Use of Surge Storage in the Waste Handling Building Reference: DOE Memorandum CBFO:OESH:GB:MN:14-1427;UFC:5487 from Mr. Jose R....

210

Criticality Safety Evaluations on the Use of 200-gram Pu Mass Limit for RHWM Waste Storage Operations  

SciTech Connect

This work establishes the criticality safety technical basis to increase the fissile mass limit from 120 grams to 200 grams for Type A 55-gallon drums and their equivalents. Current RHWM fissile mass limit is 120 grams Pu for Type A 55-gallon containers and their equivalent. In order to increase the Type A 55-gallon drum limit to 200 grams, a few additional criticality safety control requirements are needed on moderators, reflectors, and array controls to ensure that the 200-gram Pu drums remain criticality safe with inadvertent criticality remains incredible. The purpose of this work is to analyze the use of 200-gram Pu drum mass limit for waste storage operations in Radioactive and Hazardous Waste Management (RHWM) Facilities. In this evaluation, the criticality safety controls associated with the 200-gram Pu drums are established for the RHWM waste storage operations. With the implementation of these criticality safety controls, the 200-gram Pu waste drum storage operations are demonstrated to be criticality safe and meet the double-contingency-principle requirement per DOE O 420.1.

Chou, P

2011-12-14T23:59:59.000Z

211

Heating and cooling of municipal buildings with waste heat from ground water  

SciTech Connect

The feasibility of using waste heat from municipal water wells to replace natural gas for heating of the City Hall, Fire Station, and Community Hall in Wilmer, Texas was studied. At present, the 120/sup 0/F well water is cooled by dissipating the excess heat through evaporative cooling towers before entering the distribution system. The objective of the study was to determine the pumping cycle of the well and determine the amount of available heat from the water for a specified period. This data were correlated with the heating and cooling demand of the City's buildings, and a conceptual heat recovery system will be prepared. The system will use part or all of the excess heat from the water to heat the buildings, thereby eliminating the use of natural gas. The proposed geothermal retrofit of the existing natural gas heating system is not economical because the savings in natural gas does not offset the capital cost of the new equipment and the annual operating and maintenance costs. The fuel savings and power costs are a virtual trade-off over the 25-year period. The installation and operation of the system was estimated to cost $105,000 for 25 years which is an unamortized expense. In conclusion, retrofitting the City of Wilmer's municipal buildings is not feasible based on the economic analysis and fiscal projections as presented.

Morgan, D.S.; Hochgraf, J.

1980-10-01T23:59:59.000Z

212

REGIONAL BINNING FOR CONTINUED STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTES  

SciTech Connect

In the Continued Storage Analysis Report (CSAR) (Reference 1), DOE decided to analyze the environmental consequences of continuing to store the commercial spent nuclear fuel (SNF) at 72 commercial nuclear power sites and DOE-owned spent nuclear fuel and high-level waste at five Department of Energy sites by region rather than by individual site. This analysis assumes that three commercial facilities pairs--Salem and Hope Creek, Fitzpatrick and Nine-Mile Point, and Dresden and Moms--share common storage due to their proximity to each other. The five regions selected for this analysis are shown on Figure 1. Regions 1, 2, and 3 are the same as those used by the Nuclear Regulatory Commission in their regulatory oversight of commercial power reactors. NRC Region 4 was subdivided into two regions to more appropriately define the two different climates that exist in NRC Region 4. A single hypothetical site in each region was assumed to store all the SNF and HLW in that region. Such a site does not exist and has no geographic location but is a mathematical construct for analytical purposes. To ensure that the calculated results for the regional analyses reflect appropriate inventory, facility and material degradation, and radionuclide transport, the waste inventories, engineered barriers, and environmental conditions for the hypothetical sites were developed from data for each of the existing sites within the given region. Weighting criteria to account for the amount and types of SNF and HLW at each site were used in the development of the environmental data for the regional site, such that the results of the analyses for the hypothetical site were representative of the sum of the results of each actual site if they had been modeled independently. This report defines the actual site data used in development of this hypothetical site, shows how the individual site data was weighted to develop the regional site, and provides the weighted data used in the CSAR analysis. It is divided into Part 1 that defines time-dependent releases from each regional site, Part 2 that defines transport conditions through the groundwater, and Part 3 that defines transport through surface water and populations using the surface waters for drinking.

W. Lee Poe, Jr

1998-10-01T23:59:59.000Z

213

On scale and magnitude of pressure build-up induced by large-scale geologic storage of CO2  

SciTech Connect

The scale and magnitude of pressure perturbation and brine migration induced by geologic carbon sequestration is discussed assuming a full-scale deployment scenario in which enough CO{sub 2} is captured and stored to make relevant contributions to global climate change mitigation. In this scenario, the volumetric rates and cumulative volumes of CO{sub 2} injection would be comparable to or higher than those related to existing deep-subsurface injection and extraction activities, such as oil production. Large-scale pressure build-up in response to the injection may limit the dynamic storage capacity of suitable formations, because over-pressurization may fracture the caprock, may drive CO{sub 2}/brine leakage through localized pathways, and may cause induced seismicity. On the other hand, laterally extensive sedimentary basins may be less affected by such limitations because (i) local pressure effects are moderated by pressure propagation and brine displacement into regions far away from the CO{sub 2} storage domain; and (ii) diffuse and/or localized brine migration into overlying and underlying formations allows for pressure bleed-off in the vertical direction. A quick analytical estimate of the extent of pressure build-up induced by industrial-scale CO{sub 2} storage projects is presented. Also discussed are pressure perturbation and attenuation effects simulated for two representative sedimentary basins in the USA: the laterally extensive Illinois Basin and the partially compartmentalized southern San Joaquin Basin in California. These studies show that the limiting effect of pressure build-up on dynamic storage capacity is not as significant as suggested by Ehlig-Economides and Economides, who considered closed systems without any attenuation effects.

Zhou, Q.; Birkholzer, J. T.

2011-05-01T23:59:59.000Z

214

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

SciTech Connect

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

215

CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL  

SciTech Connect

RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

Farfan, E.; Coleman, R.

2011-03-31T23:59:59.000Z

216

Scenario development for the Waste Isolation Pilot Plant: Building confidence in the assessment  

SciTech Connect

Scenario development is part of the iterative performance assessment (PA) process for the Waste Isolation Pilot Plant (WIPP). Scenario development for the WIPP has been the subject of intense external review and is certain to be the subject of continued scrutiny as the project proceeds toward regulatory compliance. The principal means of increasing confidence in this aspect of the PA will be through the use of the systematic and thorough procedure toward developing the scenarios and conceptual models on which the assessment is to be based. Early and ongoing interaction with project reviewers can assist with confidence building. Quality of argument and clarity of presentation in PA will be of key concern. Appropriate tools are required for documenting and tracking assumptions, through a single assessment phase, and between iterative assessment phases. Risks associated with future human actions are of particular concern to the WIPP project, and international consensus on the principles for incorporation of future human actions in assessments would be valuable.

Galson, D.A.; Swift, P.N.

1994-07-01T23:59:59.000Z

217

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, burn Pits, and Storage Area, Nevada Test Site, Nevada  

SciTech Connect

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada (DOE/NV--963-Rev 2, dated November 2004).

U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office; Bechtel Nevada

2005-01-05T23:59:59.000Z

218

Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428  

SciTech Connect

The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed evaluation of remedial alternatives for the IWCS. (authors)

Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States)] [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

219

Waste Disposal (Illinois)  

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

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

220

Health risk assessment for the Building 3001 Storage Canal at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

This human health risk assessment has been prepared for the Environmental Restoration (ER) Program at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. The objectives of this risk assessment are to evaluate the alternatives for interim closure of the Building 3001 Storage Canal and to identify the potential health risk from an existing leak in the canal. The Building 3001 Storage Canal connects Buildings 3001 and 3019. The volume of water in the canal is monitored and kept constant at about 62,000 gal. The primary contaminants of the canal water are the radionuclides {sup 137}Cs, {sup 60}Co, and {sup 90}Sr; a layer of sediment on the canal floor also contains radionuclides and metals. The prime medium of contaminant transport has been identified as groundwater. The primary route for occupational exposure at the canal is external exposure to gamma radiation from the canal water and the walls of the canal. Similarly, the primary exposure route at the 3042 sump is external exposure to gamma radiation from the groundwater and the walls of the sump. Based on the exposure rates in the radiation work permits (Appendix C) and assuming conservative occupational work periods, the annual radiation dose to workers is considerably less than the relevant dose limits. The potential risk to the public using the Clinch River was determined for three significant exposure pathways: ingestion of drinking water; ingestion of contaminated fish; and external exposure to contaminated sediments on the shoreline, the dominant exposure pathway.

Chidambariah, V.; White, R.K.

1991-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL  

SciTech Connect

The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

1990-09-01T23:59:59.000Z

222

Analysis of accident sequences and source terms at waste treatment and storage facilities for waste generated by U.S. Department of Energy Waste Management Operations, Volume 1: Sections 1-9  

SciTech Connect

This report documents the methodology, computational framework, and results of facility accident analyses performed for the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies are assessed, and the resultant radiological and chemical source terms are evaluated. A personal computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for calculation of human health risk impacts. The methodology is in compliance with the most recent guidance from DOE. It considers the spectrum of accident sequences that could occur in activities covered by the WM PEIS and uses a graded approach emphasizing the risk-dominant scenarios to facilitate discrimination among the various WM PEIS alternatives. Although it allows reasonable estimates of the risk impacts associated with each alternative, the main goal of the accident analysis methodology is to allow reliable estimates of the relative risks among the alternatives. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also provide discussion of specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J. [and others

1995-04-01T23:59:59.000Z

223

Results from NNWSI [Nevada Nuclear Waste Storage Investigations] Series 2 bare fuel dissolution tests  

SciTech Connect

The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Two bare spent fuel specimens plus the empty cladding hulls were tested in NNWSI J-13 well water in unsealed fused silica vessels under ambient hot cell air conditions (25{degree}C) in the currently reported tests. One of the specimens was prepared from a rod irradiated in the H. B. Robinson Unit 2 reactor and the other from a rod irradiated in the Turkey Point Unit 3 reactor. Results indicate that most radionuclides of interest fall into three groups for release modeling. The first group principally includes the actinides (U, Np, Pu, Am, and Cm), all of which reached solubility-limited concentrations that were orders of magnitude below those necessary to meet the NRC 10 CFR 60.113 release limits for any realistic water flux predicted for the Yucca Mountain repository site. The second group is nuclides of soluble elements such as Cs, Tc, and I, for which release rates do not appear to be solubility-limited and may depend on the dissolution rate of fuel. In later test cycles, {sup 137}Cs, {sup 90}Sr, {sup 99}Tc, and {sup 129}I were continuously released at rates between about 5 {times} 10{sup {minus}5} and 1 {times} 10{sup {minus}4} of inventory per year. The third group is radionuclides that may be transported in the vapor phase, of which {sup 14}C is of primary concern. Detailed test results are presented and discussed. 17 refs., 15 figs., 21 tabs.

Wilson, C.N.

1990-09-01T23:59:59.000Z

224

Application of Quantitative NDE Techniques to High Level Waste Storage Tanks  

SciTech Connect

As various issues make the continued usage of high-level waste storage tanks attractive, there is an increasing need to sharpen the assessment of their structural integrity. One aspect of a structural integrity program, nondestructive evaluation, is the focus of this paper. In September 2000, a program to support the sites was initiated jointly by Tanks Focus Area and Characterization, Monitoring, and Sensor Technologies Crosscutting Program of the Office of Environmental Management, Department of Energy (DOE). The vehicle was the Center for Nondestructive Evaluation, one of the National Science Foundation's Industry/University Cooperative Research Centers that is operated in close collaboration with the Ames Laboratory, USDOE. The support activities that have been provided by the center will be reviewed. Included are the organization of a series of annual workshops to allow the sites to share experiences and develop coordinated approaches to common problems, the development of an electronic source of relevant information, and assistance of the sites on particular technical problems. Directions and early results on some of these technical assistance projects are emphasized. Included are the discussion of theoretical analysis of ultrasonic wave propagation in curved plates to support the interpretation of tandem synthetic aperture focusing data to detect flaws in the knuckle region of double shell tanks; the evaluation of guided ultrasonic waves, excited by couplant free, electromagnetic acoustic transducers, to rapidly screen for inner wall corrosion in tanks; the use of spread spectrum techniques to gain information about the structural integrity of concrete domes; and the use of magnetic techniques to identify the alloys used in the construction of tanks.

Thompson, R. B.; Rehbein, D. K.; Bastiaans, G.; Terry, M.; Alers, R.

2002-02-25T23:59:59.000Z

225

Verification survey report of the south waste tank farm training/test tower and hazardous waste storage lockers at the West Valley demonstration project, West Valley, New York  

SciTech Connect

A team from ORAU's Independent Environmental Assessment and Verification Program performed verification survey activities on the South Test Tower and four Hazardous Waste Storage Lockers. Scan data collected by ORAU determined that both the alpha and alpha-plus-beta activity was representative of radiological background conditions. The count rate distribution showed no outliers that would be indicative of alpha or alpha-plus-beta count rates in excess of background. It is the opinion of ORAU that independent verification data collected support the site?s conclusions that the South Tower and Lockers sufficiently meet the site criteria for release to recycle and reuse.

Weaver, Phyllis C.

2012-08-29T23:59:59.000Z

226

An Underground Storage Tank Integrated Demonstration report. Volume 1, Waste Characterization Data and Technology Development Needs Assessment  

SciTech Connect

The Waste Characterization Data and Technology Development Needs Assessment provides direct support to the Underground Storage Tank Integrated Demonstration (UST-ID). Key users of the study`s products may also include individuals and programs within the US Department of Energy (DOE) Office of Technology Development (EM-50), the Office of Waste Operations (EM-30), and the Office of Environmental Restoration (EM-40). The goal of this work is to provide the UST-ID with a procedure for allocating funds across competing characterization technologies in a timely and defensible manner. It resulted in three primary products: 1. It organizes and summarizes information on underground storage tank characterization data needs. 2. It describes current technology development activity related to each need and flags areas where technology development may be beneficial. 3. It presents a decision process, with supporting software, for evaluating, prioritizing, and integrating possible technology development funding packages. The data presented in this document can be readily updated as the needs of the Waste Operations and Environmental Restoration programs mature and as new and promising technology development options emerge.

Quadrel, M.J.; Hunter, V.L.; Young, J.K. [Pacific Northwest Lab., Richland, WA (United States); Lini, D.C.; Goldberg, C. [Westinghouse Hanford Co., Richland, WA (United States)

1993-04-01T23:59:59.000Z

227

Office Building Uses Ice Storage, Heat Recovery, and Cold-Air Distribution  

E-Print Network (OSTI)

Ice storage offers many opportunities to use other tcchnologies, such as heat recovery and cold-air distribution. In fact, by using them, the designer can improve the efficiency and lower the construction cost of an ice system. This paper presents a...

Tackett, R. K.

1989-01-01T23:59:59.000Z

228

A Comparative Review of Hydrologic Issues Involved in Geologic Storage of CO2 and Injection Disposal of Liquid Waste  

SciTech Connect

The paper presents a comparison of hydrologic issues and technical approaches used in deep-well injection and disposal of liquid wastes, and those issues and approaches associated with injection and storage of CO{sub 2} in deep brine formations. These comparisons have been discussed in nine areas: (1) Injection well integrity; (2) Abandoned well problems; (3) Buoyancy effects; (4) Multiphase flow effects; (5) Heterogeneity and flow channeling; (6) Multilayer isolation effects; (7) Caprock effectiveness and hydrogeomechanics; (8) Site characterization and monitoring; and (9) Effects of CO{sub 2} storage on groundwater resources There are considerable similarities, as well as significant differences. Scientifically and technically, these two fields can learn much from each other. The discussions presented in this paper should help to focus on the key scientific issues facing deep injection of fluids. A substantial but by no means exhaustive reference list has been provided for further studies into the subject.

Tsang, C.-F.; Birkholzer, J.; Rutqvist, J.

2008-04-15T23:59:59.000Z

229

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

230

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

231

Practical guidelines for small-volume additions of uninhibited water to waste storage tanks  

SciTech Connect

Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick`s second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem.

Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A.

1994-12-01T23:59:59.000Z

232

Practical guidelines for small volume additions of uninhibited water to waste storage tanks  

SciTech Connect

Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick`s second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem.

Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A. [Westinghouse Savannah River Co., Aiken, SC (United States)

1995-11-01T23:59:59.000Z

233

Plug-in electric vehicles as dispersed energy storage interactions with a smart office building  

Science Journals Connector (OSTI)

Renewable energy resources (RESs) with plug-in electric vehicles (PEVs) are being gradually accepted by society for their low carbon emission merits. However reverse power from the RES will result in the grid node's voltage rise and cause protection malfunction. As large amount of PEVs plug in the grid their overall charging power tends to be uncertain due to their complex charging behavior. At the same time if the renewable energy is integrated into the same grid the gird will face a great technological challenge. In this paper a smart building energy management system (SBEMS) is proposed to mitigate negative impact of RES and PEVs to power grid and optimize the operation of the building. The proposed SBEMS is also capable with PEVs system integration photovoltaic (PV) power forecasting optimization algorithm implementation and environmental evaluation criteria. Since PV's output is sensitive to the meteorology a 1-day-ahead power forecasting model is needed and presented. The economic system of PEVs is particularly complex because it needs optimization across multiple time steps and is strongly influenced by tariff structures. Furthermore the optimization problem to minimize the total building operational cost including PEVs charging cost is formulated while satisfying the supply and demand balance and complicated operating constraints of every energy supply equipment and devices. The simulation results have shown that the SBEMS can effectively reduce the PEVs charging cost building operation cost and the environment punishment fee. It is also important for the SBEMS to be responsible for the power grid operational indices. So the trade-off between economic consideration and load factor should be made. It is verified that the SBEMS is beneficial to the PEVs owners building operator environment and grid.

Qian Dai; Shanxu Duan; Tao Cai; Changsong Chen

2013-01-01T23:59:59.000Z

234

Biohazardous Waste Disposal GuidelinesDescriptionStorage& LabelingTreatmentDisposal  

E-Print Network (OSTI)

. Biohazard symbol on lid and sides of container. Identify waste, name of waste producer, date of culture. Off-site treatment by VEHS. Address: U-0211 MCN 1161 21st Ave S Nashville, TN 37232-2665 615-322-2057 Off-site

Wikswo, John

235

A charging control strategy for active building-integrated thermal energy storage systems using frequency domain modeling  

Science Journals Connector (OSTI)

Abstract Primary space conditioning can be provided through active building-integrated thermal energy storage (BITES) systems, such as radiant space heating through concrete slabs. This approach can reduce peak space conditioning demand and energy costs while satisfying thermal comfort. However, thermal charging rates need to be predictively controlled due to the slow thermal response of BITES systems. This paper presents a charge control strategy using frequency domain models and room air temperature set-point profile as input. The models were previously verified with full-scale experiment data. The calculation procedures are demonstrated on active BITES systems with and without airflow to zone. Results show that the calculated charging rates satisfy the desired room air temperature set-point profiles. This control strategy is important for integrating the design and operation of active BITES systems because frequency domain models also provide important design information.

Yuxiang Chen; Andreas K. Athienitis; Khaled E. Galal

2014-01-01T23:59:59.000Z

236

Pressure Build?Up in LNG and LH2 Vehicular Cryogenic Storage Tanks  

Science Journals Connector (OSTI)

The use of LNG and LH2 as fuels in heavy duty vehicles is increasing steadily because cryogenic liquids provides superior volumetric and gravimetric energy densities compared to other means of on?board storage. Although several sizes and types of tanks exist a typical vehicular storage tank has a volume of ?400 liters (?100 gallons). The pressure in the ullage space of a tank freshly filled is usually ?0.25 MPa but may vary during use from ?0.25 MPa (?20 psig) to ?0.92 MPa (?120 psig). Cryogenic vehicular tanks are typically dual?walled stainless steel vessels with vacuum and superinsulation isolation between the inner and outer vessel walls. The heat leaks into such tanks are measured as a percentage boil?off per day. For a storage tank of vehicular size range the boil?off may be ? 1 % day depending upon the cryogen and the quality of the tank. The corresponding heat leak into the cryogenic liquid vaporizes a certain amount of liquid that in turn increases the pressure in the tank which in turn significantly influences the properties of the cryogens. We have used a novel approach to calculate the increase in pressure of LNG and LH2 in a closed cryogenic vessel with a fixed heat leak as a function of time using real equations of state for the properties of the cryogens. The method and results for the time it takes for a freshly filled tank to increase in pressure from the filling pressure of ?0.25 MPa to a venting pressure of ?1.73 MPa are presented.

J. A. Barclay; A. M. Rowe; M. A. Barclay

2004-01-01T23:59:59.000Z

237

Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect

Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

1996-12-01T23:59:59.000Z

238

Permitted Mercury Storage Facility Notifications | Department...  

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

Services Waste Management Waste Disposition Long-Term Management and Storage of Elemental Mercury is in the Planning Stages Permitted Mercury Storage Facility...

239

Modelling of the shielding capabilities of the existing solid radioactive waste storages at ignalina NPP  

Science Journals Connector (OSTI)

......primary circuit, gas circuit and turbines. Furthermore, it...waste conditioning technology was changed. Before...However, during the SAR development INPP started introducing...Starting from the SAR development time compartment no......

Arturas Smaizys; Povilas Poskas; Valdas Ragaisis

2005-12-20T23:59:59.000Z

240

Revision to the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of Transuranic Waste 9/6/02)  

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

989 989 Federal Register / Vol. 67, No. 173 / Friday, September 6, 2002 / Notices 1 The only exception to this decision was the Sandia National Laboratory in New Mexico, which will ship its TRU waste to the Los Alamos National Laboratory for disposal preparation and storage before disposal at WIPP. SANDEL, E. A. MS. SAUL, E. L. MR. SCHAEFER, J. C. MR. SCHAEFER JR, W. J. MR. SCHNEIDER, P. A. MR. SCHREGARDOUS, D. R. MR. SCHUBERT, D. CAPT SHEA, R. M. MAJGEN SHECK, E. E. MR. SHEPHARD, M. R. MS. SIMON, E. A. MR. SOMOROFF, A. R. DR. STELLOH-GARNER, C. MS. STOREY, R. C. MR. STUSSIE, W. A. MR. SULLIVAN, P. E. RADML TAMBURRINO, P. M. MR. TARRANT, N. J. MS. TESCH, T. G. MR. THOMAS, J. R. BGEN THOMAS, R. O. MR. THOMPSON, R. C. MR. THROCKMORTON JR., E. L. MR. TOWNSEND, D. K. MS.

Note: This page contains sample records for the topic "waste storage building" 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

Better Buildings Challenge to Cut Energy Waste Grows by 1 Billion Square Feet  

Office of Energy Efficiency and Renewable Energy (EERE)

Building on President Obama’s Climate Action Plan and the Administration’s Better Buildings Challenge, the Energy Department announced today that Better Buildings Challenge partners are on track to meet their energy performance goals in their second year, saving approximately $100 million a year.

242

Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility  

SciTech Connect

As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to overpressure--external to T Plant, was included for completeness but is not within the scope of the hazards evaluation. Container failures external to T Plant will be addressed as part of the transportation analysis. This document describes the HazOp analysis performed for the activities associated with the storage of SNF sludge in the T Plant.

SCHULTZ, M.V.

2000-08-22T23:59:59.000Z

243

Use of the Modified Light Duty Utility Arm to Perform Nuclear Waste Cleanup of Underground Waste Storage Tanks at Oak Ridge National Laboratory  

SciTech Connect

The Modified Light Duty Utility Arm (MLDUA) is a selectable seven or eight degree-of-freedom robot arm with a 16.5 ft (5.03 m) reach and a payload capacity of 200 lb. (90.72 kg). The utility arm is controlled in either joystick-based telerobotic mode or auto sequence robotics mode. The MLDUA deployment system deploys the utility arm vertically into underground radioactive waste storage tanks located at Oak Ridge National Laboratory. These tanks are constructed of gunite material and consist of two 25 ft (7.62 m) diameter tanks in the North Tank Farm and six 50 ft (15.24 m) diameter tanks in the South Tank Farm. After deployment inside a tank, the utility arm reaches and grasps the confined sluicing end effecter (CSEE) which is attached to the hose management arm (HMA). The utility arm positions the CSEE within the tank to allow the HMA to sluice the tank's liquid and solid waste from the tank. The MLDUA is used to deploy the characterization end effecter (CEE) and gunite scarifying end effecter (GSEE) into the tank. The CEE is used to survey the tank wall's radiation levels and the physical condition of the walls. The GSEE is used to scarify the tank walls with high-pressure water to remove the wall scale buildup and a thin layer of gunite which reduces the radioactive contamination that is embedded into the gunite walls. The MLDUA is also used to support waste sampling and wall core-sampling operations. Other tools that have been developed for use by the MLDUA include a pipe-plugging end effecter, pipe-cutting end effecter, and pipe-cleaning end effecter. Washington University developed advance robotics path control algorithms for use in the tanks. The MLDUA was first deployed in June 1997 and has operated continuously since then. Operational experience in the first four tanks remediated is presented in this paper.

Blank, J.A.; Burks, B.L.; DePew, R.E.; Falter, D.D.; Glassell, R.L.; Glover, W.H.; Killough, S.M.; Lloyd, P.D.; Love, L.J.; Randolph, J.D.; Van Hoesen, S.D.; Vesco, D.P.

1999-04-01T23:59:59.000Z

244

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...

245

Method for extracting metals from aqueous waste streams for long term storage  

DOE Patents (OSTI)

A liquid--liquid extraction method for removing metals and hydrous metal colloids from waste streams is provided wherein said waste streams are contacted with a solvent system containing a water-in-oil microemulsion wherein the inverted micelles contain the extracted metal. A silicon alkoxide, either alone or in combination with other metal alkoxide compounds is added to the water-in-oil microemulsion, thereby allowing encapsulation of the extracted metal within a silicon oxide network. Lastly, the now-encapsulated metal is precipitated from the water-in-oil microemulsion phase to yield aggregates of metal-silicate particles having average individual particle sizes of approximately 40 nanometers.

Chaiko, David J. (Woodridge, IL)

1995-01-01T23:59:59.000Z

246

Method for extracting metals from aqueous waste streams for long term storage  

DOE Patents (OSTI)

A liquid-liquid extraction method for removing metals and hydrous metal colloids from waste streams is provided wherein said waste streams are contacted with a solvent system containing a water-in-oil microemulsion wherein the inverted micelles contain the extracted metal. A silicon alkoxide, either alone or in combination with other metal alkoxide compounds is added to the water-in-oil microemulsion, thereby allowing encapsulation of the extracted metal within a silicon oxide network. Lastly, the now-encapsulated metal is precipitated from the water-in-oil microemulsion phase to yield aggregates of metal-silicate particles having average. individual particle sizes of approximately 40 manometers.

Chaiko, D.J.

1993-01-01T23:59:59.000Z

247

DOE/EIS-0283-SA-2: Supplement Analysis for Waste Solidification Building - Surplus Plutonium Program EIS (11/08)  

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

I I ~ ~ I Y I ~ L ' I I I i f l 7 c r [ y S r ~ for (lon~lr~rclion (711d Operal~on of n IVa~tr Solrd~fi~trtron Burlding at the S(rvannn/z I ? I I . ~ I Srte DOEIEIS-0283-SA-2 SUPPLEMENT ANALYSIS WASTE SOLIDIFICATION BUILDING I N T R O D U C T I O N A N D PURPOSE The National Nuclear Security Administration (NNSA), a separately organized agency within the U.S. Department of Energy (DOE), is proposing to construct and operate a standalone Waste Solidification E3uilding1 (WSR) in F-Area at the Savannah River Site (SRS) near Aiken, South Carolina. Certain liquid low-level radioactive waste (LLW) and liquid transuranic (TRU) waste expected to be generated in the Mixed Oxide Fuel Fabrication Facility (MFFF) and Pit Disassembly and Conversion Facility (PDCF) as part of the U.S. Surplus Plutonium Disposition Program woi~ld be treated and

248

Increased Levels of Markers of Microbial Exposure in Homes with Indoor Storage of Organic Household Waste  

Science Journals Connector (OSTI)

...Levels of Markers of Microbial Exposure in Homes with Indoor Storage of Organic Household...might increase microbial exposure in the home environment. In this study we evaluated...House dust samples were collected in 99 homes in The Netherlands selected on the basis...

Inge M. Wouters; Jeroen Douwes; Gert Doekes; Peter S. Thorne; Bert Brunekreef; Dick J. J. Heederik

2000-02-01T23:59:59.000Z

249

Site characterization plan: Conceptual design report: Volume 6, Drawing portfolio: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 6 contains drawings. 114 figs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

250

Phase 5 storage (Project W-112) Central Waste Complex operational readiness review, final report  

SciTech Connect

This document is the final report for the RFSH conducted, Contractor Operational Readiness Review (ORR) for the Central Waste Complex (CWC) Project W-112 and Interim Safety Basis implementation. As appendices, all findings, observations, lines of inquiry and the implementation plan are included.

Wight, R.H.

1997-05-30T23:59:59.000Z

251

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7  

SciTech Connect

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

Not Available

1994-04-01T23:59:59.000Z

252

Summary of environmental characterization activities at the Oak Ridge National Laboratory Solid Waste Storage Area Six, FY 1986 through 1987  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP), has supported characterization activities in Solid Waste Storage Area (SWSA 6) to acquire information necessary for identification and planning of remedial actions that may be warranted, and to facilitate eventual closure of the site. In FY 1986 investigations began in the areas of site hydrology, geochemistry, soils, geology, and geohydrologic model application. This report summarizes work carried out in each of these areas during FY`s 1986 and 1987 and serves as a status report pulling together the large volume of data that has resulted. Characterization efforts are by no means completed; however, a sufficient data base has been generated to begin data interpretation and analysis of site contaminants.

Davis, E.C.; Solomon, D.K.; Dreier, R.B.; Lee, S.Y.; Kelmers, A.D.; Lietzke, D.A. [Oak Ridge National Lab., TN (United States); Craig, P.M. [Environmental Consulting Engineers, Inc., Knoxville, TN (United States)

1987-09-30T23:59:59.000Z

253

Summary of environmental characterization activities at the Oak Ridge National Laboratory Solid Waste Storage Area Six, FY 1986 through 1987  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP), has supported characterization activities in Solid Waste Storage Area (SWSA 6) to acquire information necessary for identification and planning of remedial actions that may be warranted, and to facilitate eventual closure of the site. In FY 1986 investigations began in the areas of site hydrology, geochemistry, soils, geology, and geohydrologic model application. This report summarizes work carried out in each of these areas during FY's 1986 and 1987 and serves as a status report pulling together the large volume of data that has resulted. Characterization efforts are by no means completed; however, a sufficient data base has been generated to begin data interpretation and analysis of site contaminants.

Davis, E.C.; Solomon, D.K.; Dreier, R.B.; Lee, S.Y.; Kelmers, A.D.; Lietzke, D.A. (Oak Ridge National Lab., TN (United States)); Craig, P.M. (Environmental Consulting Engineers, Inc., Knoxville, TN (United States))

1987-09-30T23:59:59.000Z

254

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1  

SciTech Connect

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection.

Burt, D.L.

1994-04-01T23:59:59.000Z

255

Federal Buildings Supplemental Survey 1993  

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

mobile homes and trailers, even if they housed commercial activity; and oil storage tanks. (See Commercial Building and Nonresidential Building.) Building Envelope or Shell...

256

An evaluation of robust controls for passive building thermal mass and mechanical thermal energy storage under uncertainty  

Science Journals Connector (OSTI)

Abstract Passive building thermal mass and mechanical thermal energy storage (TES) are known as one of state-of-the-art demand-side control instruments. Specifically, Model-based Predictive Control (MPC) for this operation has the potential to significantly increase performance and bring economic advantages. However, due to the uncertainty in certain operating conditions in the field, its control effectiveness could be diminished and/or seriously damaged, which results in poor performance. This study pursues improvements of the control performance of both thermal inventories under uncertainty by proposing a robust MPC in which relevant uncertainty sources are compiled; therefore, it is designed to perform more stable than traditional \\{MPCs\\} under uncertain conditions. Uniqueness and superiority of the proposed robust demand-side controls include: (i) Controls are developed based on the a priori uncertainty assessment, such that a systematic modeling approach for uncertainty was taken according to characteristics and classifications of uncertainty. (ii) The robust MPC reduces the variability of performance under varied and non-indigenous conditions compared to the deterministic MPC, and thus can avoid the worst case situation.

Sean Hay Kim

2013-01-01T23:59:59.000Z

257

Imaging through obscurations for sluicing operations in the waste storage tanks  

SciTech Connect

Waste remediators have identified that surveillance of waste remediation operations and periodic inspections of stored waste are required under very demanding and difficult viewing environments. In many cases, obscurants such as dust or water vapor are generated as part of the remediation activity. Methods are required for viewing or imaging beyond the normal visual spectrum. Work space images guide the movement of remediation equipment, creating a need for rapidly updated, near real-time imaging capability. In addition, there is a need for three-dimensional topographical data to determine the contours of the wastes, to plan retrieval campaigns, and to provide a three-dimensional map of a robot`s work space as basis for collision avoidance. Three basic imaging techniques were evaluated: optical, acoustic and radar. The optical imaging methods that were examined used cameras which operated in the visible region and near-infrared region and infrared cameras which operated in the 3--5 micron and 8--12 micron wavelength regions. Various passive and active lighting schemes were tested, as well as the use of filters to eliminate reflection in the visible region. Image enhancement software was used to extend the range where visual techniques could be used. In addition, the operation of a laser range finder, which operated at 0.835 microns, was tested when fog/water droplets were suspended in the air. The acoustic technique involved using commercial acoustic sensors, operating at approximately 50 kHz and 215 kHz, to determine the attenuation of the acoustic beam in a high-humidity environment. The radar imaging methods involved performing millimeter wave (94 GHz) attenuation measurement sin the various simulated sluicing environments and performing preliminary experimental imaging studies using a W-Band (75--110 GHz) linearly scanned transceiver in a laboratory environment. The results of the tests are discussed.

Peters, T.J.; McMakin, D.L.; Sheen, D.M.; Chieda, M.A.

1994-08-01T23:59:59.000Z

258

Building the institutional capacity for managing commercial high-level radioactive waste  

SciTech Connect

In July 1981, the Office of Nuclear Waste Management of the Department of Energy contracted with the National Academy of Public Administration for a study of institutional issues associated with the commercial radioactive waste management program. The two major sets of issues which the Academy was asked to investigate were (1) intergovernmental relationships, how federal, state, local and Indian tribal council governments relate to each other in the planning and implementation of a waste management program, and (2) interagency relationships, how the federal agencies with major responsibilities in this public policy arena interact with each other. The objective of the study was to apply the perspectives of public administration to a difficult and controversial question - how to devise and execute an effective waste management program workable within the constraints of the federal system. To carry out this task, the Academy appointed a panel composed of individuals whose background and experience would provide the several types of knowledge essential to the effort. The findings of this panel are presented along with the executive summary. The report consists of a discussion of the search for a radioactive waste management strategy, and an analysis of the two major groups of institutional issues: (1) intergovernmental, the relationship between the three major levels of government; and (2) interagency, the relationships between the major federal agencies having responsibility for the waste management program.

None

1982-05-01T23:59:59.000Z

259

TWRS Retrieval and Storage Mission and Immobilized Low Activity Waste (ILAW) Disposal Plan  

SciTech Connect

This project plan has a twofold purpose. First, it provides a waste stream project plan specific to the River Protection Project (RPP) (formerly the Tank Waste Remediation System [TWRS] Project) Immobilized Low-Activity Waste (LAW) Disposal Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-90-01 (Ecology et al. 1994) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan (Ecology et al. 1998). Second, it provides an upper tier document that can be used as the basis for future subproject line-item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 [DOE 1992] and 430.1 [DOE 1995a]). The format and content of this project plan are designed to accommodate the requirements mentioned by the Tri-Party Agreement and the DOE orders. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

BURBANK, D.A.

1999-09-01T23:59:59.000Z

260

CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

2003-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Waste Prevention in the Ecological Building Project of Delft University of Technology  

Science Journals Connector (OSTI)

A multidisciplinairy workinggroup of 8 departments from 3 faculties of the Delft University of Technology is carrying out a research on energy saving building and environmental technology. The preliminary desi...

ir. Hans Hubers

1987-01-01T23:59:59.000Z

262

West Valley Demonstration Project Prepares to Relocate High-Level Waste |  

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

West Valley Demonstration Project Prepares to Relocate High-Level West Valley Demonstration Project Prepares to Relocate High-Level Waste West Valley Demonstration Project Prepares to Relocate High-Level Waste December 24, 2013 - 12:00pm Addthis The West Valley Demonstration Project’s high-level waste canisters will be relocated to interim onsite storage. The West Valley Demonstration Project's high-level waste canisters will be relocated to interim onsite storage. The first group of eight concrete storage casks for the West Valley Demonstration Project’s high-level waste. The first group of eight concrete storage casks for the West Valley Demonstration Project's high-level waste. Site subcontractor American DND completed demolition of the contaminated 01-14 Building in 2013. Site subcontractor American DND completed demolition of the contaminated

263

West Valley Demonstration Project Prepares to Relocate High-Level Waste |  

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

West Valley Demonstration Project Prepares to Relocate High-Level West Valley Demonstration Project Prepares to Relocate High-Level Waste West Valley Demonstration Project Prepares to Relocate High-Level Waste December 24, 2013 - 12:00pm Addthis The West Valley Demonstration Project’s high-level waste canisters will be relocated to interim onsite storage. The West Valley Demonstration Project's high-level waste canisters will be relocated to interim onsite storage. The first group of eight concrete storage casks for the West Valley Demonstration Project’s high-level waste. The first group of eight concrete storage casks for the West Valley Demonstration Project's high-level waste. Site subcontractor American DND completed demolition of the contaminated 01-14 Building in 2013. Site subcontractor American DND completed demolition of the contaminated

264

Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Firre Protection System Design  

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

the the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1

265

Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Firre Protection System Design  

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

the the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1

266

Building a Parallel Cloud Storage System using OpenStack’s Swift Object Store and Transformative Parallel I/O  

SciTech Connect

Our project consists of bleeding-edge research into replacing the traditional storage archives with a parallel, cloud-based storage solution. It used OpenStack's Swift Object Store cloud software. It's Benchmarked Swift for write speed and scalability. Our project is unique because Swift is typically used for reads and we are mostly concerned with write speeds. Cloud Storage is a viable archive solution because: (1) Container management for larger parallel archives might ease the migration workload; (2) Many tools that are written for cloud storage could be utilized for local archive; and (3) Current large cloud storage practices in industry could be utilized to manage a scalable archive solution.

Burns, Andrew J. [Los Alamos National Laboratory; Lora, Kaleb D. [Los Alamos National Laboratory; Martinez, Esteban [Los Alamos National Laboratory; Shorter, Martel L. [Los Alamos National Laboratory

2012-07-30T23:59:59.000Z

267

Life Cycle cost Analysis of Waste Heat Operated Absorption Cooling Systems for Building HVAC Applications  

E-Print Network (OSTI)

was used to calculate the PWC of the system for annual operating hours of 8760 and the same is compared with the electric based vapour compression chiller (VCRS) of same capacity. The life cycle cost (LCC) of waste heat operated absorption chiller...

Saravanan, R.; Murugavel, V.

2010-01-01T23:59:59.000Z

268

Repository sealing plan for the Nevada Nuclear Waste Storage Investigations Project, fiscal years 1984 through 1990  

SciTech Connect

This report presents a plan to develop acceptable sealing methods for a prospective nuclear waste repository in unsaturated tuff in Yucca Mountain, which is on and adjacent to the Nevada Test Site. Sealing is the permanent closure of the underground facility, shafts, ramps, and boreholes. Questiona associated with the performance of the sealing system form the basis for this plan. Tasks that contribute to the resolution of these questions and support the documentation required for the construction authorization application are proposed. The approach to answering the performance-related questions is divided into six steps: (1) assess the need for sealing, (2) define the design requirements, (3) measure the material properties, (4) assess the performance of sealing designs, (5) perform laboratory analyses and field testing, and (6) reassess the performance of sealing designs. Organization of the tasks supporting each step is illustrated by detailed work-flow diagrams.

Fernandez, J.A.

1985-02-01T23:59:59.000Z

269

Geochemical information for sites contaminated with low-level radioactive wastes: II. St. Louis Airport Storage Site  

SciTech Connect

The St. Louis Airport Storage Site (SLASS) became radioactively contaminated as a result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy is considering various remedial action options for the SLASS under the Formerly Utilized Site Remedial Action Program (FUSRAP). This report describes the results of geochemical investigations, carried out to support the FUSRAP activities and to aid in quantifying various remedial action options. Soil and groundwater samples from the site were characterized, and sorption ratios for uranium and radium and apparent concentration limit values for uranium were measured in soil/groundwater systems by batch contact methodology. The uranium and radium concentrations in soil samples were significantly above background near the old contaminated surface horizon (now at the 0.3/sup -/ to 0.9/sup -/m depth); the maximum values were 1566 ..mu..g/g and 101 pCi/g, respectively. Below about the 6/sup -/m depth, the concentrations appeared to be typical of those naturally present in soils of this area (3.8 +- 1.2 ..mu..g/g and 3.1 +- 0.6 pCi/g). Uranium sorption ratios showed stratigraphic trends but were generally moderate to high (100 to 1000 L/kg). The sorption isotherm suggested an apparent uranium concentration limit of about 200 mg/L. This relatively high solubility can probably be correlated with the carbonate content of the soil/groundwater systems. The lower sorption ratio values obtained from the sorption isotherm may have resulted from changes in the experimental procedure or the groundwater used. The SLASS appears to exhibit generally favorable behavior for the retardation of uranium solubilized from waste in the site. Parametric tests were conducted to estimate the sensitivity of uranium sorption and solubility to the pH and carbonate content of the system.

Seeley, F.G.; Kelmers, A.D.

1985-01-01T23:59:59.000Z

270

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

271

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

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

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

272

Supplemental design requirements document enhanced radioactive and mixed waste storage: Phase 5, Project W-113  

SciTech Connect

This Supplemental Design Requirements Document (SDRD) is used to communicate Project W-113 specific plant design information from Westinghouse Hanford Company (WHC) to the United States Department of Energy (DOE) and the cognizant Architect Engineer (A/E). The SDRD is prepared after the completion of the project Conceptual Design report (CDR) and prior to the initiation of definitive design. Information in the SDRD serves two purposes: to convey design requirements that are too detailed for inclusion in the Functional Design Criteria (FDC) report and to serve as a means of change control for design commitments in the Title I and Title II design. The Solid Waste Retrieval Project (W-113) SDRD has been restructured from the equipment based outline used in previous SDRDs to a functional systems outline. This was done to facilitate identification of deficiencies in the information provided in the initial draft SDRD and aid design confirmation. The format and content of this SDRD adhere as closely as practicable to the requirements of WHC-CM-6-1, Standard Engineering Practices for Functional Design Criteria.

Ocampo, V.P.

1994-11-01T23:59:59.000Z

273

Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project, August 2011  

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

Review of Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project May 2011 August 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Scope ...................................................................................................................................................... 1 3.0 Background ............................................................................................................................................ 2

274

Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project, July 2011  

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

Independent Review of Independent Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project July 2011 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ......................................................................................................................................1 2.0 Scope .........................................................................................................................................1 3.0 Background ...............................................................................................................................2

275

Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project, August 2011  

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

Review of Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project May 2011 August 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Scope ...................................................................................................................................................... 1 3.0 Background ............................................................................................................................................ 2

276

Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project, July 2011  

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

Independent Review of Independent Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project July 2011 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ......................................................................................................................................1 2.0 Scope .........................................................................................................................................1 3.0 Background ...............................................................................................................................2

277

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

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

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

278

Model Predictive Control for Energy Efficient Buildings  

E-Print Network (OSTI)

Learning Control for Thermal Energy Storage Systems”. In:Predictive Control of Thermal Energy Storage in Buildingmaking use of building thermal energy storage, and this work

Ma, Yudong

2012-01-01T23:59:59.000Z

279

Decommissioning of TA-21-153, a /sup 227/Ac contaminated old filter building  

SciTech Connect

An exhaust air filter building contaminated with /sup 227/Ac was decommissioned at the Los Alamos National Laboratory, Los Alamos, New Mexico, in 1978. The building was constructed in the late 1940s to clean exhaust air from several buildings at TA-21, DP Site. It was in service until March 1970. The project involved preliminary decontamination, dismantling the building, and burying the debris at an on-site waste disposal/storage area. This report presents the details on the decommissioning procedures, health physics, waste management, environmental surveillance, and costs for the operation.

Harper, J.R.; Garde, R.

1981-11-01T23:59:59.000Z

280

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

Bailey, L.L.

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy`s (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency`s (EPA`s) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

Bailey, L.L.

1991-12-31T23:59:59.000Z

282

Corrective Action Investigation Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada, July 2002, Rev. No. 0  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 140 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 140 consists of nine Corrective Action Sites (CASs): 05-08-01, Detonation Pits; 05-08-02, Debris Pits; 05-17-01, Hazardous Waste Accumulation Site (Buried); 05-19-01, Waste Disposal Site; 05-23-01, Gravel Gertie; 05-35-01, Burn Pit; 05-99-04, Burn Pit; 22-99-04, Radioactive Waste Dump; 23-17-01, Hazardous Waste Storage Area. All nine of these CASs are located within Areas 5, 22, and 23 of the Nevada Test Site (NTS) in Nevada, approximately 65 miles northwest of Las Vegas. This CAU is being investigated because disposed waste may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. The NTS has been used for various research and development projects including nuclear weapons testing. The CASs in CAU 140 were used for testing, material storage, waste storage, and waste disposal. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution criteria and resolve the decision statements. Phase I will determine if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels. This data will be evaluated at all CASs. Phase II will determine the extent of the contaminant(s) of concern (COCs). This data will only be evaluated for CASs with a COC identified during Phase I. Based on process knowledge, the COPCs for CAU 140 include volatile organics, semivolatile organics, petroleum hydrocarbons, explosive residues, herbicides, pesticides, polychlorinated biphenyls, metals, and radionuclides. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NV

2002-07-18T23:59:59.000Z

283

Synergic and conflicting issues in planning underground use to produce energy in densely populated countries, as Italy: Geological storage of CO2, natural gas, geothermics and nuclear waste disposal  

Science Journals Connector (OSTI)

In densely populated countries there is a growing and compelling need to use underground for different and possibly coexisting technologies to produce “low carbon” energy. These technologies include (i) clean coal combustion merged with CO2 Capture and Storage (CCS); (ii) last-generation nuclear power or, in any case, safe nuclear wastes disposal, both “temporary” and “geological” somewhere in Europe (at least in one site): Nuclear wastes are not necessarily associated to nuclear power plants; (iii) safe natural gas (CH4) reserves to allow consumption also when the foreign pipelines are less available or not available for geopolitical reasons and (iv) “low-space-consuming” renewables in terms of Energy Density Potential in Land (EDPL measured in [GW h/ha/year]) as geothermics. When geothermics is exploited as low enthalpy technology, the heat/cool production could be associated, where possible, to increased measures of “building efficiency”, low seismic risks building reworking and low-enthalpy heat managing. This is undispensable to build up “smart cities”. In any case the underground geological knowledge is prerequisite. All these technologies have been already proposed and defined by the International Energy Agency (IEA) Road Map 2009 as priorities for worldwide security: all need to use underground in a rational and safe manner. The underground is not renewable in most of case histories [10,11]. IEA recently matched and compared different technologies in a unique “Clean Energy Economy” improved document (Paris, November 16–17, 2011), by the contribution of this vision too (see reference). In concert with “energy efficiency” improvement both for plants and buildings, in the frame of the “smart cities” scenarios, and the upstanding use of “energy savings”, the energetic planning on regional scale where these cities are located, are strategic for the year 2050: this planning is strongly depending by the underground availability and typology. Therefore, if both literature and European Policy are going fast to improve the concept of “smart cities” this paper stresses the concept of “smart regions”, more strategic than “smart cities”, passing throughout a discussion on the synergic and conflicting use of underground to produce energy for the “smart regions” as a whole. The paper highlights the research lines which are urgent to plan the soundest energy mix for each region by considering the underground performances case by case: a worldwide mapping, by GIS tools of this kind of information could be strategic for all the “world energy management” authorities, up to ONU, with its Intergovernmental Panel on Climate Change (IPCC), the G20, the Carbon Sequestration Leadership Forum (CSLF) and the European Platforms such as the “Zero Emissions Fossil Fuel Power Plants” (EU-ZEP Platform), the Steel Platform, the Biomass Platform too. All of these organizations agree on the need for synergistic and coexistent uses of underground for geological storage of CO2, CH4, nuclear waste and geothermic exploitation. The paper is therefore a discussion of the tools, methods and approaches to these underground affecting technologies, after a gross view of the different uses of underground to produce energy for each use, with their main critical issues (i.e. public acceptance in different cases). The paper gives some gross evaluation for the Lazio Region and some hints from the Campania Region, located in Central Italy. Energy Density Potential in Land (EDPL), is calculated for each renewable energy technology (solar, wind, geothermal) highlighting the potentiality of the last. Why the Italian case history among the densely populated countries? on the Italian territory is hard to find suitable areas (mostly if greenfields) to use the own underground, with respect to other European countries, due to the presence of seismotectonic activity and many faulted areas characterized by Diffuse Degassing Structures (DDSs, which are rich in CO2 and CH4). In this cases, public acceptan

Fedora Quattrocchi; Enzo Boschi; Angelo Spena; Mauro Buttinelli; Barbara Cantucci; Monia Procesi

2013-01-01T23:59:59.000Z

284

Sandia National Laboratories: Batteries & Energy Storage Publications  

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

Radioactive Waste Prioritized Safeguards and Security Issues for extended Storage of Used Nuclear Fuel Research to Improve Transportation Energy Storage Fact Sheet Sandia's Battery...

285

Numerical modelling and experimental studies of thermal behaviour of building integrated thermal energy storage unit in a form of a ceiling panel  

Science Journals Connector (OSTI)

AbstractObjective The paper presents a new concept of building integrated thermal energy storage unit and novel mathematical and numerical models of its operation. This building element is made of gypsum based composite with microencapsulated PCM. The proposed heat storage unit has a form of a ceiling panel with internal channels and is, by assumption, incorporated in a ventilation system. Its task is to reduce daily variations of ambient air temperature through the absorption (and subsequent release) of heat in PCM, without additional consumption of energy. Methods The operation of the ceiling panel was investigated experimentally on a special set-up equipped with temperature sensors, air flow meter and air temperature control system. Mathematical and numerical models of heat transfer and fluid flow in the panel account for air flow in the panel as well as real thermal properties of the PCM composite, i.e.: thermal conductivity variation with temperature and hysteresis of enthalpy vs. temperature curves for heating and cooling. Proposed novel numerical simulator consists of two strongly coupled sub models: the first one – 1D – which deals with air flowing through the U-shaped channel and the second one – 3D – which deals with heat transfer in the body of the panel. Results Spatial and temporal air temperature variations, measured on the experimental set-up, were used to validate numerical model as well as to get knowledge of thermal performance of the panel operating in different conditions. Conclusion Preliminary results of experimental tests confirmed the ability of the proposed heat storage unit to effectively control the air temperature inside the building. However, detailed measurement of the temperature of PCM composite have shown some disadvantages of the panel used in the study, e.g. thickness of the walls and distribution of PCM should be optimized. This can be achieved with the aid of the numerical simulator developed in this research. Practical implications The proposed ceiling panel, optimised from the point of view of thermal performance in a given environmental conditions, can be used as a part of ventilation systems in residential and office buildings.

Maciej Jaworski; Piotr ?apka; Piotr Furma?ski

2014-01-01T23:59:59.000Z

286

Regional geological assessment of the Devonian-Mississippian shale sequence of the Appalachian, Illinois, and Michigan basins relative to potential storage/disposal of radioactive wastes  

SciTech Connect

The thick and regionally extensive sequence of shales and associated clastic sedimentary rocks of Late Devonian and Early Mississippian age has been considered among the nonsalt geologies for deep subsurface containment of high-level radioactive wastes. This report examines some of the regional and basin-specific characteristics of the black and associated nonblack shales of this sequence within the Appalachian, Illinois, and Michigan basins of the north-central and eastern United States. Principal areas where the thickness and depth of this shale sequence are sufficient to warrant further evaluation are identified, but no attempt is made to identify specific storage/disposal sites. Also identified are other areas with less promise for further study because of known potential conflicts such as geologic-hydrologic factors, competing subsurface priorities involving mineral resources and groundwater, or other parameters. Data have been compiled for each basin in an effort to indicate thickness, distribution, and depth relationships for the entire shale sequence as well as individual shale units in the sequence. Included as parts of this geologic assessment are isopach, depth information, structure contour, tectonic elements, and energy-resource maps covering the three basins. Summary evaluations are given for each basin as well as an overall general evaluation of the waste storage/disposal potential of the Devonian-Mississippian shale sequence,including recommendations for future studies to more fully characterize the shale sequence for that purpose. Based on data compiled in this cursory investigation, certain rock units have reasonable promise for radioactive waste storage/disposal and do warrant additional study.

Lomenick, T.F.; Gonzales, S.; Johnson, K.S.; Byerly, D.

1983-01-01T23:59:59.000Z

287

Review of private sector and Department of Energy treatment, storage, and disposal capabilities for low-level and mixed low-level waste  

SciTech Connect

Private sector capacity for treatment, storage, and disposal (TSD) of various categories of radioactive waste has been researched and reviewed for the Idaho National Engineering Laboratory (INEL) by Lockheed Idaho Technologies Company, the primary contractor for the INEL. The purpose of this document is to provide assistance to the INEL and other US Department of Energy (DOE) sites in determining if private sector capabilities exist for those waste streams that currently cannot be handled either on site or within the DOE complex. The survey of private sector vendors was limited to vendors currently capable of, or expected within the next five years to be able to perform one or more of the following services: low-level waste (LLW) volume reduction, storage, or disposal; mixed LLW treatment, storage, or disposal; alpha-contaminated mixed LLW treatment; LLW decontamination for recycling, reclamation, or reuse; laundering of radioactively-contaminated laundry and/or respirators; mixed LLW treatability studies; mixed LLW treatment technology development. Section 2.0 of this report will identify the approach used to modify vendor information from previous revisions of this report. It will also illustrate the methodology used to identify any additional companies. Section 3.0 will identify, by service, specific vendor capabilities and capacities. Because this document will be used to identify private sector vendors that may be able to handle DOE LLW and mixed LLW streams, it was decided that current DOE capabilities should also be identified. This would encourage cooperation between DOE sites and the various states and, in some instances, may result in a more cost-effective alternative to privatization. The DOE complex has approximately 35 sites that generate the majority of both LLW and mixed LLW. Section 4.0 will identify these sites by Operations Office, and their associated LLW and mixed LLW TSD units.

Willson, R.A.; Ball, L.W.; Mousseau, J.D.; Piper, R.B.

1996-03-01T23:59:59.000Z

288

Comparative Assessment of Status and Opportunities for CO2 Capture and Storage and Radioactive Waste Disposal in North America  

E-Print Network (OSTI)

and liability for carbon capture and sequestration, Environ.Wilson and Gerard, editors, Carbon Capture and SequestrationSpecial Report on carbon dioxide capture and storage, ISBN

Oldenburg, C.

2010-01-01T23:59:59.000Z

289

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

allows high temperature waste heat utilization. Phosphoricnatural gas chillers, waste heat or solar heat; • hot wateris limited by generated waste heat Regulatory constraints: -

Stadler, Michael

2009-01-01T23:59:59.000Z

290

Hanford Waste Transfer Planning and Control - 13465  

SciTech Connect

Hanford tank waste cleanup requires efficient use of double-shell tank space to support single-shell tank retrievals and future waste feed delivery to the Waste Treatment and Immobilization Plant (WTP). Every waste transfer, including single-shell tank retrievals and evaporator campaign, is evaluated via the Waste Transfer Compatibility Program for compliance with safety basis, environmental compliance, operational limits and controls to enhance future waste treatment. Mixed radioactive and hazardous wastes are stored at the Hanford Site on an interim basis until they can be treated, as necessary, for final disposal. Implementation of the Tank Farms Waste Transfer Compatibility Program helps to ensure continued safe and prudent storage and handling of these wastes within the Tank Farms Facility. The Tank Farms Waste Transfer Compatibility Program is a Safety Management Program that is a formal process for evaluating waste transfers and chemical additions through the preparation of documented Waste Compatibility Assessments (WCA). The primary purpose of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures as the result of waste transfer operations. The program defines a consistent means of evaluating compliance with certain administrative controls, safety, operational, regulatory, and programmatic criteria and specifies considerations necessary to assess waste transfers and chemical additions. Current operations are most limited by staying within compliance with the safety basis controls to prevent flammable gas build up in the tank headspace. The depth of solids, the depth of supernatant, the total waste depth and the waste temperature are monitored and controlled to stay within the Compatibility Program rules. Also, transfer planning includes a preliminary evaluation against the Compatibility Program to assure that operating plans will comply with the Waste Transfer Compatibility Program. (authors)

Kirch, N.W.; Uytioco, E.M.; Jo, J. [Washington River Protection Solutions, LLC, Richland, Washington (United States)] [Washington River Protection Solutions, LLC, Richland, Washington (United States)

2013-07-01T23:59:59.000Z

291

Resource Conservation and Recovery Act (RCRA) Part B permit application for tank storage units at the Oak Ridge Y-12 Plant  

SciTech Connect

In compliance with the Resource Conservation and Recovery Act (RCRA), this report discusses information relating to permit applications for three tank storage units at Y-12. The storage units are: Building 9811-1 RCRA Tank Storage Unit (OD-7); Waste Oil/Solvent Storage Unit (OD-9); and Liquid Organic Solvent Storage Unit (OD-10). Numerous sections discuss the following: Facility description; waste characteristics; process information; groundwater monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plan, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification. Sixteen appendices contain such items as maps, waste analyses and forms, inspection logs, equipment identification, etc.

Not Available

1994-05-01T23:59:59.000Z

292

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

storage, thermal storage, solar thermal collectors, PVs, andis disallowed; 5. a low storage, PV, and solar thermal priceW run 4 force low storage / PV and solar thermal results run

Stadler, Michael

2009-01-01T23:59:59.000Z

293

Dedicated-site, interim storage of high-level nuclear waste as part of the management system  

Science Journals Connector (OSTI)

...develop permanent repositories. A systems approach...reprocessed nuclear wastes from fuel rods...In- teragency Review Group (1) and...high-level wastes, including both...mined geologic repositories for permanent...Under current plans for mined geologic...and performance standards of permanent...

E-an Zen

1980-01-01T23:59:59.000Z

294

Transforming Commercial Building Operations  

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

Transforming Commercial Building Operations Transforming Commercial Building Operations Transforming Commercial Building Operations Ron Underhill Pacific Northwest National Laboratory ronald.underhill@pnnl.gov (509)375-9765 April 4, 2013 2 | Building Technologies Office eere.energy.gov * Most buildings are not commissioned (Cx) before occupancy, including HVAC and lighting systems * Buildings often are poorly operated and maintained leading to significant energy waste of 5 to 20%, even when they have building automation systems (BASs)

295

Transforming Commercial Building Operations  

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

Transforming Commercial Building Operations Transforming Commercial Building Operations Transforming Commercial Building Operations Ron Underhill Pacific Northwest National Laboratory ronald.underhill@pnnl.gov (509)375-9765 April 4, 2013 2 | Building Technologies Office eere.energy.gov * Most buildings are not commissioned (Cx) before occupancy, including HVAC and lighting systems * Buildings often are poorly operated and maintained leading to significant energy waste of 5 to 20%, even when they have building automation systems (BASs)

296

Westinghouse Waste Simulation and Optimization Software Tool - 13493  

SciTech Connect

Radioactive waste is produced during NPP operation and NPP D and D. Different kinds of waste with different volumes and properties have to be treated. Finding a technically and commercially optimized waste treatment concept is a difficult and time consuming process. The Westinghouse waste simulation and optimization software tool is an approach to study the total life cycle cost of any waste management facility. The tool enables the user of the simulation and optimization software to plan processes and storage buildings and to identify bottlenecks in the overall waste management design before starting detailed planning activities. Furthermore, application of the software enables the user to optimize the number of treatment systems, to determine the minimum design capacity for onsite storage facilities, to identify bottlenecks in the overall design and to identify the most cost-effective treatment paths by maintaining optimal waste treatment technologies. In combination with proven waste treatment equipment and integrated waste management solutions, the waste simulation and optimization software provides reliable qualitative results that lead to an effective planning and minimization of the total project planning risk of any waste management activity. (authors)

Mennicken, Kim [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany); Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)

2013-07-01T23:59:59.000Z

297

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

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

1334E-2009 1334E-2009 Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States Michael Stadler, Chris Marnay, Afzal Siddiqui, Judy Lai, Brian Coffey, and Hirohisa Aki Environmental Energy Technologies Division Revised March 2009 http://eetd.lbl.gov/EA/EMP/emp-pubs.html The work described in this paper was funded by the Office of Electricity Delivery and Energy Reliability, Renewable and Distributed Systems Integration Program in the U.S. Department of Energy under Contract No. DE-AC02- 05CH11231. ERNEST ORLANDO LAWRENCE BERKELEY NATIONAL LABORATORY Disclaimer This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct

298

THERMAL IMPACT OF WASTE EMPLACEMENT AND SURFACE COOLING ASSOCIATED WITH GEOLOGIC DISPOSAL OF NUCLEAR WASTE  

E-Print Network (OSTI)

d long-term storage and even methods for centralized waste •long-term storage of spent fuel, interim storage of high levei wastestorage of solid wastes of IAEA categories 3 and 4. 5) studies of long-term

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

299

Systems Approach for Safe Handling and Quality Assurance in Waste Management: Conditioning, Transport, Storage, Disposal and Safeguards  

Science Journals Connector (OSTI)

Thus, waste product and canister quality assurance measures must be oriented towards criteria derived from their overall safety assessments. The most stringent requirements originate from long-term safety aspects...

E. R. Merz

1996-01-01T23:59:59.000Z

300

Physicochemical Processes Occurring in Long-Term Storage of Liquid Radioactive Waste in Deep Underground Collector Beds  

Science Journals Connector (OSTI)

Interaction under hydrothermal conditions (pressure 3 MPa; temperature 80-170°C; contact time up to 2500 h) of intermediate-level acidic waste with bed rock of the underground repository for liquid radioactive...

E. V. Zakharova; E. P. Kaimin; E. N. Darskaya; K. A. Menyailo…

2001-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Application of the NNWSI [Nevada Nuclear Waste Storage Investigations] unsaturated test method to actinide doped SRL [Savannah River Laboratory] 165 type glass  

SciTech Connect

The results of tests done using the Unsaturated Test Method are presented. These tests, done to determine the suitability of glass in a potential high-level waste repository as developed by the Nevada Nuclear Waste Storage Investigations Project, simulate conditions anticipated for the post-containment phase of the repository when only limited contact between the waste form and water is expected. The reaction of glass occurs via processes that are initiated due to glass/water vapor and glass/liquid water contact. Vapor interaction results in the initiation of an exchange process between water and the more mobile species (alkalis and boron) in the glass. The liquid reaction produces interactions similar to those seen in standard leaching tests, except due to the limited amount of water present and the presence of partially sensitized 304L stainless steel, the formation of reaction products greatly exceeds that found in MCC-1 type leach tests. The effect of sensitized stainless steel on the reaction is to enhance breakdown of the glass matrix thereby increasing the release of the transuranic elements from the glass. However, most of the Pu and Am released is entrained by either the metal components of the test or by the reaction phases, and is not released to solution. 16 refs., 20 figs., 17 tabs.

Bates, J.K.; Gerding, T.J.

1990-08-01T23:59:59.000Z

302

Accelerated safety analyses - structural analyses Phase I - structural sensitivity evaluation of single- and double-shell waste storage tanks  

SciTech Connect

Accelerated Safety Analyses - Phase I (ASA-Phase I) have been conducted to assess the appropriateness of existing tank farm operational controls and/or limits as now stipulated in the Operational Safety Requirements (OSRs) and Operating Specification Documents, and to establish a technical basis for the waste tank operating safety envelope. Structural sensitivity analyses were performed to assess the response of the different waste tank configurations to variations in loading conditions, uncertainties in loading parameters, and uncertainties in material characteristics. Extensive documentation of the sensitivity analyses conducted and results obtained are provided in the detailed ASA-Phase I report, Structural Sensitivity Evaluation of Single- and Double-Shell Waste Tanks for Accelerated Safety Analysis - Phase I. This document provides a summary of the accelerated safety analyses sensitivity evaluations and the resulting findings.

Becker, D.L.

1994-11-01T23:59:59.000Z

303

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

natural gas chillers, waste heat or solar heat; • hot wateris limited by generated waste heat Regulatory constraints: -might favor the use of waste heat from DG units or from

Stadler, Michael

2009-01-01T23:59:59.000Z

304

Hazardous Waste Management (Oklahoma)  

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

305

Solid Waste Operations Complex (SWOC) Facilities Sprinkler System Hydraulic Calculations  

SciTech Connect

The attached calculations demonstrate sprinkler system operational water requirements as determined by hydraulic analysis. Hydraulic calculations for the waste storage buildings of the Central Waste Complex (CWC), T Plant, and Waste Receiving and Packaging (WRAP) facility are based upon flow testing performed by Fire Protection Engineers from the Hanford Fire Marshal's office. The calculations received peer review and approval prior to release. The hydraulic analysis program HASS Computer Program' (under license number 1609051210) is used to perform all analyses contained in this document. Hydraulic calculations demonstrate sprinkler system operability based upon each individual system design and available water supply under the most restrictive conditions.

KERSTEN, J.K.

2003-07-11T23:59:59.000Z

306

Site characterization plan: Conceptual design report, Volume 2: Chapters 4-9: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. 147 refs., 145 figs., 83 tabs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

307

Site characterization plan: Conceptual design report, Volume 3: Appendices A-E: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. Volume 3 contains Appendices A through E.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

308

Utilizing New Binder Materials for Green Building has Zero Waste by Recycling Slag and Sewage Sludge Ash  

E-Print Network (OSTI)

binding material to save energy and to produce new innovative zero materials waste . The current research aims to investigate new binder materials as alternative of Portland cement. Alkali activated slag (AAS) blended with sewage sludge ash (SSA...

Zeedan, S. R.

2010-01-01T23:59:59.000Z

309

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-12-31T23:59:59.000Z

310

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-01-01T23:59:59.000Z

311

Thermal energy storage technical progress report, April 1990--March 1991  

SciTech Connect

The Department of Energy (DOE) is supporting development of thermal energy storage (TES) as a means of efficiently coupling energy supplies to variable heating or cooling demands. Uses of TES include electrical demand-side management in buildings and industry, extending the utilization of renewable energy resources such as solar, and recovery of waste heat from periodic industrial processes. Technical progress to develop TES for specific diurnal and industrial applications under Oak Ridge National Laboratory's TES program from April 1990 to March 1992 is reported and covers research in the areas of low temperature sorption, direct contact ice making, latent heat storage plasterboard and latent/sensible heat regenerator technology development.

Tomlinson, J.J.

1992-03-01T23:59:59.000Z

312

Thermal energy storage technical progress report, April 1990--March 1991  

SciTech Connect

The Department of Energy (DOE) is supporting development of thermal energy storage (TES) as a means of efficiently coupling energy supplies to variable heating or cooling demands. Uses of TES include electrical demand-side management in buildings and industry, extending the utilization of renewable energy resources such as solar, and recovery of waste heat from periodic industrial processes. Technical progress to develop TES for specific diurnal and industrial applications under Oak Ridge National Laboratory`s TES program from April 1990 to March 1992 is reported and covers research in the areas of low temperature sorption, direct contact ice making, latent heat storage plasterboard and latent/sensible heat regenerator technology development.

Tomlinson, J.J.

1992-03-01T23:59:59.000Z

313

Spent fuel test-climax: a test of geologic storage of high-level waste in granite  

SciTech Connect

A test of retrievable geologic storage of spent fuel assemblies from an operating commercial nuclear reactor is underway at the Nevada Test Site (NTS) of the US Department of Energy. This generic test is located 420 m below the surface in the Climax granitic stock. Eleven canisters of spent fuel approximately 2.5 years out of reactor core (about 1.6 kW/canister thermal output) were emplaced in a storage drift along with 6 electrical simulator canisters. Two adjacent drifts contain electrical heaters, which are operated to simulate within the test array the thermal field of a large repository. Fuel was loaded during April to May 1980 and initial results of the test will be presented.

Ramspott, L.D.; Ballou, L.B.; Patrick, W.C.

1981-01-01T23:59:59.000Z

314

Waste Isolation Pilot Plant (WIPP) fact sheet  

SciTech Connect

Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all terms and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993.

Not Available

1993-10-01T23:59:59.000Z

315

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

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

MacDougall, H R; Scully, L W; Tillerson, J R [comps.] [comps.

1987-09-01T23:59:59.000Z

316

Site characterization plan: Conceptual design report: Volume 5, Appendices P-R: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect

The site for the prospective respository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 5 contains appendices P through R.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

317

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator  

SciTech Connect

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Deckers, Jan; Mols, Ludo [Belgoprocess NV, Operations Department, Gravenstraat 73, B-2480 Dessel (Belgium)

2007-07-01T23:59:59.000Z

318

Radiotoxicity and decay heat power of spent nuclear fuel of VVER type reactors at long-term storage  

Science Journals Connector (OSTI)

......a controllable storage facility for cooling...transferred for long-term storage. The storage...adequately handle waste radiation characteristics...type reactors at long-term storage. | Radiotoxicity...of radioactive waste (radwaste) determines......

B. R. Bergelson; A. S. Gerasimov; G. V. Tikhomirov

2005-12-20T23:59:59.000Z

319

Sandia National Laboratories: Building a Microgrid  

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

cold thermal storage. "All will interconnect with our building through a control room and building management system," Barrera said. A number of Japanese companies are...

320

Design/Installation and Structural Integrity Assessment of the Bethel Valley Low-Level Waste Collection and Transfer System Upgrade for Building 3544 (Process Waste Treatment Plant) at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

This document describes and assesses planned modifications to be made to the Building 3544 Process Waste Treatment Plant of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in response to the requirements of the Federal Facility Agreement (FFA) relating to environmental protection requirements for tank systems. The modifications include the provision of a new double contained LLW line replacing an existing buried line that does not provide double containment. This new above ground, double contained pipeline is provided to permit discharge of treated process waste fluid to an outside truck loading station. The new double contained discharge line is provided with leak detection and provisions to remove accumulated liquid. An existing LLW transfer pump, concentrated waste tank, piping and accessories are being utilized, with the addition of a secondary containment system comprised of a dike, a chemically resistant internal coating on the diked area surfaces and operator surveillance on a daily basis for the diked area leak detection. This assessment concludes that the planned modifications comply with applicable requirements of Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation.

NONE

1996-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Radioactive waste management and decommissioning of accelerator facilities  

Science Journals Connector (OSTI)

......the removed radioactive waste shall be treated and processed for either long-term storage or disposal. delayed...facility itself becomes a long-term storage that shall be...dismantling resources, waste storage space or development......

Luisa Ulrici; Matteo Magistris

2009-11-01T23:59:59.000Z

322

Large Scale Energy Storage  

Science Journals Connector (OSTI)

This work is mainly an experimental investigation on the storage of solar energy and/or the waste heat of a ... lake or a ground cavity. A model storage unit of (1×2×0.75)m3 size was designed and constructed. The...

F. Çömez; R. Oskay; A. ?. Üçer

1987-01-01T23:59:59.000Z

323

Integration of remediation strategy with waste management capabilities and regulatory drivers for radioactive waste storage tanks at the Oak Ridge National Laboratory  

SciTech Connect

This paper addresses the plans and strategies for remediation of the Liquid Low-Level Waste (LLLW) system tanks that have been removed from service at the Oak Ridge National Laboratory (ORNL). The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facility Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy Oak Ridge Operations Office (DOE-ORO), the EPA-Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One requirement of the FFA is that LLLW tanks that are removed from service must be evaluated and remediated through the CERCLA process. The Environmental Restoration Program intends to meet this requirement by using a {open_quotes}streamlined{close_quote} approach for selected tanks. This approach will combine the CERCLA Site Investigation. Remedial Action, Feasibility Study, and Proposed Plan requirements into a single Interim Proposed Plan document. This streamlined approach is expected to reduce the time required to complete the regulatory process while attaining acceptable risk reduction in a cost-effective way.

Baxter, J.T. [H& R Technical Associates, Inc., Oak Ridge, TN (United States); Hepworth, H.K. [Northern Arizona Univ., Flagstaff, AZ (United States); Hooyman, J.H. [Oak Ridge National Lab., TN (United States)

1995-04-01T23:59:59.000Z

324

Plan for integrated testing for NNWSI [Nevada Nuclear Waste Storage Investigations] non EQ3/6 data base portion  

SciTech Connect

The purposes of the Integrated Testing Task are to develop laboratory data on thermodynamic properties for actinide and fission product elements for use in the EQ3/6 geochemical modelling code; to determine the transport properties of radionuclides in the near-field environment; and develop and validate a model to describe the rate of release of radionuclides from the near-field environment. Activities to achieve the firs item have been described in the Scientific Investigation Plan for EQ3/6, where quality assurance levels were assigned to the acitivities. This Scientific Investigation Plan describes activities to achieve the second and third purposes. The information gathered in these activities will be used to assess compliance with the performance objective for the Engineered Barrier System (EBS) to control the rate of release of radionuclides if the repository license application includes part of the host rock; to provide a source term for release of radionuclides from the waste package near-field environment to the system performance assessment task for use in showing compliance with the Environmental Protection Agency requirements; and to provide a source term for release of radionculides from the waste package near-field environment to the system performance assessment task for use in doing calculations of cumulative releases of radionuclides from the repository over 100,000 years as required by the site evaluation process. 5 refs.

Oversby, V.M.

1987-05-29T23:59:59.000Z

325

Plutonium Finishing Plan (PFP) Treatment and Storage Unit Interim Status Closure Plan  

SciTech Connect

This document describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) Treatment and Storage Unit. The PFP Treatment and Storage Unit is located within the 234-52 Building in the 200 West Area of the Hanford Facility. Although this document is prepared based upon Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the 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 PFP Treatment and Storage Unit manages transuranic mixed (TRUM) waste, there are many controls placed on management of the waste. Based on the many controls placed on management of TRUM waste, releases of TRUM waste are not anticipated to occur in the PFP Treatment and Storage Unit. Because the intention is to clean close the PFP Treatment and Storage Unit, postclosure activities are not applicable to this closure plan. To clean close the 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 is environmentally impractical, the closure plan will be modified to address required postclosure activities. The PFP Treatment and Storage Unit will be operated to immobilize and/or repackage plutonium-bearing waste in a glovebox process. The waste to be processed is in a solid physical state (chunks and coarse powder) and will be sealed into and out of the glovebox in closed containers. The containers of immobilized waste will be stored in the glovebox and in additional permitted storage locations at PFP. The waste will be managed to minimize the potential for spills outside the glovebox, and to preclude spills from reaching soil. Containment surfaces will be maintained to ensure integrity. In the unlikely event that a waste spill does occur outside the glovebox, operating methods and administrative controls will require that waste spills be cleaned up promptly and completely, and a notation will be 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.

PRIGNANO, A.L.

2000-07-01T23:59:59.000Z

326

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

acid batteries flow battery thermal n/a n/a xiv The Effectslead/acid battery) and thermal storage, capabilities, withlifetime (a) thermal storage 1 flow battery 220$/kWh and

Stadler, Michael

2009-01-01T23:59:59.000Z

327

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

efficiency requirements - Maximum emission limits Investment constraints: - Payback period is constrained Storage constraints: - Electricity stored is limited by battery

Stadler, Michael

2009-01-01T23:59:59.000Z

328

Spent Fuel and Waste Management Activities for Cleanout of the 105 F Fuel Storage Basin at Hanford  

SciTech Connect

Clean-out of the F Reactor fuel storage basin (FSB) by the Environmental Restoration Contractor (ERC) is an element of the FSB decontamination and decommissioning and is required to complete interim safe storage (ISS) of the F Reactor. Following reactor shutdown and in preparation for a deactivation layaway action in 1970, the water level in the F Reactor FSB was reduced to approximately 0.6 m (2 ft) over the floor. Basin components and other miscellaneous items were left or placed in the FSB. The item placement was performed with a sense of finality, and no attempt was made to place the items in an orderly manner. The F Reactor FSB was then filled to grade level with 6 m (20 ft) of local surface material (essentially a fine sand). The reactor FSB backfill cleanout involves the potential removal of spent nuclear fuel (SNF) that may have been left in the basin unintentionally. Based on previous cleanout of four water-filled FSBs with similar designs (i.e., the B, C, D, and DR FSBs in the 1980s), it was estimated that up to five SNF elements could be discovered in the F Reactor FSB (1). In reality, a total of 10 SNF elements have been found in the first 25% of the F Reactor FSB excavation. This paper discusses the technical and programmatic challenges of performing this decommissioning effort with some of the controls needed for SNF management. The paper also highlights how many various technologies were married into a complete package to address the issue at hand and show how no one tool could be used to complete the job; but by combining the use of multiple tools, progress is being made.

Morton, M. R.; Rodovsky, T. J.; Day, R. S.

2002-02-25T23:59:59.000Z

329

Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design, May 2013  

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

HIAR SRS-2013-5-07 HIAR SRS-2013-5-07 Site: Savannah River Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Savannah River Site (SRS) Waste Solidification Building (WSB) Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design Dates of Activity : 05/07/2013 - 05/09/2013 Report Preparer: Joseph Lenahan Activity Description/Purpose: 1. Review the corrective actions being implemented by the construction contractor to address Findings 1-4, 6, and 9 from a construction quality review performed by the Office of Health, Safety and Security (HSS) (Reference 1). 2. Meet with the SRS WSB project staff and Savannah River Nuclear Solutions (SRNS) engineers to discuss the

330

Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design, May 2013  

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

HIAR SRS-2013-5-07 HIAR SRS-2013-5-07 Site: Savannah River Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Savannah River Site (SRS) Waste Solidification Building (WSB) Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design Dates of Activity : 05/07/2013 - 05/09/2013 Report Preparer: Joseph Lenahan Activity Description/Purpose: 1. Review the corrective actions being implemented by the construction contractor to address Findings 1-4, 6, and 9 from a construction quality review performed by the Office of Health, Safety and Security (HSS) (Reference 1). 2. Meet with the SRS WSB project staff and Savannah River Nuclear Solutions (SRNS) engineers to discuss the

331

309 Building transition plan  

SciTech Connect

The preparation for decontamination and decommissioning (transition) of the 309 Building is projected to be completed by the end of the fiscal year (FY) 1998. The major stabilization and decontamination efforts include the Plutonium Recycle Test Reactor (PRTR), fuel storage and transfer pits, Transfer Waste (TW) tanks and the Ion Exchange Vaults. In addition to stabilizing contaminated areas, equipment, components, records, waste products, etc., will be dispositioned. All nonessential systems, i.e., heating, ventilation, and air conditioning (HVAC), electrical, monitoring, fluids, etc., will be shut down and drained/de-energized. This will allow securing of the process, laboratory, and office areas of the facility. After that, the facility will be operated at a level commensurate with its surveillance needs while awaiting D&D. The implementation costs for FY 1995 through FY 1998 for the transition activities are estimated to be $1,070K, $2,115K, $2,939K, and $4,762K, respectively. Costs include an assumed company overhead of 20% and a 30% out year contingency.

Graves, C.E.

1994-08-31T23:59:59.000Z

332

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect

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

333

Independent regulatory examination of radiation situation in the areas of spent nuclear fuel and radioactive wastes storage in the Russian far east  

Science Journals Connector (OSTI)

......submarines performing reception and storage of spent nuclear fuel (SNF...as well as for temporary storage and reloading of SNF after...seaweeds, bottom sediments, seawater, sea fish, mushrooms, local...for LRW treatment, the LRW storage facility, SRW storage facility......

N. K. Shandala; S. M. Kiselev; A. I. Lucyanec; A. V. Titov; V. A. Seregin; D. V. Isaev; S. V. Akhromeev

2011-07-01T23:59:59.000Z

334

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4  

SciTech Connect

Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms.

Not Available

1994-04-01T23:59:59.000Z

335

Evaluation of the TORE(R)Lance for Radioactive Waste Mobilization and Retrieval from Underground Storage Tanks  

SciTech Connect

The TORE? Lance is a hand-held hydro transportation device with the ability to convey solids at pre-determined slurry concentrations over great distances. The TORE? Lance head generates a precessing vortex core to mobilize solids. Solids retrieval is accomplished using an eductor. The device contains no parts and requires pressurized fluid to operate the eductor and produce mobilization. Three configurations of TORE? Lance operation were evaluated for mobilization and eduction during these tests: compressed air, water, and an air and water mixture. These tests have shown that the TORE? Lance is a tool that can be used at Hanford for mobilization and retrieval of wastes. The system is versatile and can be configured for many types of applications. These studies showed that the diverse applications require unique solutions so care is recommended for TORE? Lance equipment selection for each application. The two components of the TORE? Lance are the precessing vortex for mobilizing and the eductor for retrieval. The precessing vortex is sensitive to fluid flow rate and pressure. In the hand-held unit these parameters are controlled both internally, by changing shim spacing, and externally by controlling the flow split between the eductor and the head. For in-tank applications out-of-tank control of both these parameters are recommended.

Bamberger, Judith A.; Bates, Cameron J.; Bates, James M.; White, M.

2002-09-25T23:59:59.000Z

336

Corrective Action Decision Document for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada: Revision No. 0  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of a recommended corrective action alternative appropriate to facilitate the closure of Corrective Action Unit (CAU) 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 5, 22, and 23 of the NTS, CAU 140 consists of nine corrective action sites (CASs). Investigation activities were performed from November 13 through December 11, 2002, with additional sampling to delineate the extent of contaminants of concern (COCs) conducted on February 4 and March 18 and 19, 2003. Results obtained from the investigation activities and sampling indicated that only 3 of the 9 CASs at CAU 140 had COCs identified. Following a review of existing data, future land use, and current operations at the NTS, the following preferred alternatives were developed for consideration: (1) No Further Action - six CASs (05-08-02, 05-17-01, 05-19-01, 05-35-01, 05-99-04, and 22-99-04); (2) Clean Closure - one CAS (05-08-01), and (3) Closure-in-Place - two CASs (05-23-01 and 23-17-01). These alternatives were judged to meet all requirements for the technical components evaluated. Additionally, the alternatives meet all applicable state and federal regulations for closure of the site and will eliminate potential future exposure pathways to the contaminated media at CAU 140.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-10-17T23:59:59.000Z

337

Evaluation and Optimization of Underground Thermal Energy Storage Systems of Energy Efficient Buildings (WKSP)- A Project within the new German R&D- Framework EnBop  

E-Print Network (OSTI)

Until 2003 the research on buildings in operation in Germany focused mainly on demonstration buildings. Starting with the EVA project managed by IGS the attention is shifting towards performance in operation. The paper gives a general review...

Bockelmann, F.; Kipry, H.; Plesser, S.; Fisch, M. N.

338

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

339

Building a World of Difference  

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

Waste?to?Energy Roadmapping Workshop Building a World of Difference Presentation by Patricia Scanlan, Director of Residuals Treatment Technologies, Black & Veatch

340

Optimizing Distributed Energy Resources and Building Retrofits with the Strategic DER-CAModel  

E-Print Network (OSTI)

technology (as PV, solar thermal, storage, fuel cells,building with thermal storage and solar- To be published inphotovoltaic; ST: solar thermal; BS: battery storage; TS:

Stadler, Michael

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Moving Toward Zero Energy Buildings  

E-Print Network (OSTI)

, appliances, etc) and systems integration to optimize the performance of the building. Then we need the best renewable energy technologies that can be incorporated into buildings: solar, small wind, and geothermal heat pumps (some day hydrogen storage..., appliances, etc) and systems integration to optimize the performance of the building. Then we need the best renewable energy technologies that can be incorporated into buildings: solar, small wind, and geothermal heat pumps (some day hydrogen storage...

Ginsberg, M.

2008-01-01T23:59:59.000Z

342

Evaluate Greenhouse Gas Reduction Strategies for Buildings |...  

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

office buildings, Program B can evaluate other key building types (i.e., storage and hospital facilities) using the same approach. Once all key building types are evaluated, the...

343

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

capture solar radiation and convert it into thermal energy.solar thermal collector (kW) PV (kW) electric storage (kWh) flow battery - energy (solar thermal collector ( kW) PV (kW) electric storage (kWh) flow battery - energy (

Stadler, Michael

2009-01-01T23:59:59.000Z

344

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

capture solar radiation and convert it into thermal energy.solar thermal collector (kW) PV (kW) electric storage (kWh) flow battery - energy (solar thermal collector (kW) PV (kW) electric storage (kWh) flow battery - energy (

Stadler, Michael

2009-01-01T23:59:59.000Z

345

Thermal energy storage technical progress report, April 1992--March 1993  

SciTech Connect

The Department of Energy (DOE) is supporting development of thermal energy storage (TES) as a means of efficiently coupling energy supplies to variable heating or cooling demands. Uses of TES include electrical demand-side management in buildings and industry, extending the utilization of renewable energy resources such as solar, and recovery of waste heat from periodic industrial processes. Technical progress to develop TES for specific diurnal and industrial applications under the Oak Ridge National Laboratory`s TES program from April 1992 to March 1993 is reported and covers research in the areas of low temperature sorption, thermal energy storage water heater, latent heat storage wallboard and latent/sensible heat regenerator technology development.

Olszewski, M.

1993-05-01T23:59:59.000Z

346

1999 Commercial Buildings Characteristics--Principal Building Activities  

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

Principal Building Activities Principal Building Activities Principal Building Activities Three of the four activities that dominated commercial floorspace-office, warehouse and storage, and mercantile-dominated the distribution of buildings (Figure 1). Each of these three activity categories included more than 600,000 buildings, while no other building activity had more than a half-million buildings and only service buildings exceeded 350,000 buildings. Detailed tables Figure 1. Distribution of Buildings by Principal Building Activity, 1999 Figure 1. Distribution of Buildings by Principal Building Activity, 1999. If having trouble viewing this page, please contact the National Energy Information Center at (202) 586-8800. Energy Information Administration Commercial Buildings Energy Consumption Survey

347

Hanford high-level waste evaporator/crystallizer corrosion evaluation  

SciTech Connect

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

348

Economic Passive Solar Warm-Air Heating and Ventilating System Combined with Short Term Storage within Building Components for Residential Houses  

Science Journals Connector (OSTI)

Warm-air heating systems are very suitable for the exploitation of solar energy. A relatively low temperature level combined ... used for transportation and distribution equipment or as storage elements.

K. Bertsch; E. Boy; K.-D. Schall

1984-01-01T23:59:59.000Z

349

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

acid batteries flow battery thermal n/a n/a xiv The Effectscapacity electrical flow battery thermal n/a n/a source:lead/acid battery) and thermal storage, capabilities, with

Stadler, Michael

2009-01-01T23:59:59.000Z

350

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

capitalcost.htm). EPRI-DOE Handbook of Energy Storage foret al. 1996, 2003, EPRI-DOE Handbook 2003, Goldstein, L. etet al. 2003, EPRI-DOE Handbook 2003 and at the Electricity

Stadler, Michael

2009-01-01T23:59:59.000Z

351

Effect of Heat and Electricity Storage and Reliability on Microgrid Viability: A Study of Commercial Buildings in California and New York States  

E-Print Network (OSTI)

et al. 1996, 2003, EPRI-DOE Handbook 2003, Goldstein, L. etet al. 2003, EPRI-DOE Handbook 2003 and at the Electricitycapitalcost.htm). EPRI-DOE Handbook of Energy Storage for

Stadler, Michael

2009-01-01T23:59:59.000Z

352

A Look at Principal Building Activities in Commercial Buildings  

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

Home > Commercial Buildings Home> Special Topics > 1995 Principal Home > Commercial Buildings Home> Special Topics > 1995 Principal Building Activities Office Education Health Care Retail and Service Food Service Food Sales Lodging Religious Worship Public Assembly Public Order and Safety Warehouse and Storage Vacant Other Summary Comparison Table (All Activities) More information on the: Commercial Buildings Energy Consumption Survey A Look at ... Principal Building Activities in the Commercial Buildings Energy Consumption Survey (CBECS) When you look at a city skyline, most of the buildings you see are commercial buildings. In the CBECS, commercial buildings include office buildings, shopping malls, hospitals, churches, and many other types of buildings. Some of these buildings might not traditionally be considered "commercial," but the CBECS includes all buildings that are not residential, agricultural, or industrial.

353

University Buildings Landmark Buildings  

E-Print Network (OSTI)

KEY University Buildings Landmark Buildings The Lanyon Building Roads Footpath Cafe Grass Queen's University Belfast Campus Map The Lanyon Building The Students' Union The David Keir Building School Offices and Sonic Arts Q Nursing and Midwifery R Pharmacy S Planning, Architecture and Civil Engineering T Politics

Paxton, Anthony T.

354

University Buildings Landmark Buildings  

E-Print Network (OSTI)

KEY University Buildings Landmark Buildings The Lanyon Building Roads Footpath Cafe University Accommodation Queen's University Belfast Campus Map The Lanyon Building The Students' Union The David Keir Building School Offices A Biological Sciences B Chemistry and Chemical Engineering C Education D

Müller, Jens-Dominik

355

University Buildings Landmark Buildings  

E-Print Network (OSTI)

KEY University Buildings Landmark Buildings The Lanyon Building Roads Footpath Cafe University Engineering N Medicine, Dentistry and Biomedical Sciences P Music and Sonic Arts Q Nursing and Midwifery R and Student Affairs 3 Administration Building 32 Ashby Building 27 Belfast City Hospital 28 Bernard Crossland

Paxton, Anthony T.

356

Derr Track Storage Bldg Sigma Alpha  

E-Print Network (OSTI)

!( Derr Track Storage Bldg Solar House Entomology Lab Bldg Sigma Alpha Epsilon 11 MEAS Ocean Lab & Storage Avent Ferry Complex Building Sigma Phi Epsilon 7 Pi Kappa Alpha 10 Sigma Alpha Mu 4 Tau Kappa

Reeves, Douglas S.

357

Underground Storage Tanks: New Fuels and Compatibility  

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

Breakout Session 1C—Fostering Technology Adoption I: Building the Market for Renewables with High Octane Fuels Underground Storage Tanks: New Fuels and Compatibility Ryan Haerer, Program Analyst, Alternative Fuels, Office of Underground Storage Tanks, Environmental Protection Agency

358

The Rocky Flats Plant Waste Stream and Residue Identification and Characterization Program (WSRIC): Progress and achievements  

SciTech Connect

The Waste Stream and Residue Identification and Characterization (WSRIC) Program, as described in the WSRIC Program Description delineates the process knowledge used to identify and characterize currently-generated waste from approximately 5404 waste streams originating from 576 processes in 288 buildings at Rocky Flats Plant (RFP). Annual updates to the WSRIC documents are required by the Federal Facilities Compliance Agreement between the US Department of Energy, the Colorado Department of Health and the Environmental Protection Agency. Accurate determination and characterization of waste is a crucial component in RFP`s waste management strategy to assure compliance with Resource Conservation and Recovery Act (RCRA) storage and treatment requirements, as well as disposal acceptance criteria. The WSRIC Program was rebaselined in September 1992, and serves as the linchpin for documenting process knowledge in RFP`s RCRA operating record. Enhancements to the WSRIC include strengthening the waste characterization rationale, expanding WSRIC training for waste generators, and incorporating analytical information into the WSRIC building books. These enhancements will improve credibility with the regulators and increase waste generators` understanding of the basis for credible waste characterizations.

Ideker, V.L. [EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant; Doyle, G.M. [USDOE Rocky Flats Office, Golden, CO (United States)

1994-02-01T23:59:59.000Z

359

Farm Buildings Research  

Science Journals Connector (OSTI)

... THE first supplement, 1958-61, of Part 3, Buildings for Poultry, issued by the Agricultural Research Council, has recently been published (Pp. ... . 71. London: Agricultural Research Council, 1963. 4s.). This bibliography of farm buildings research provides important basic information: in the past, much waste has occurred from the ...

1963-07-27T23:59:59.000Z

360

Buildings Energy Data Book: 5.5 Thermal Distribution Systems  

Buildings Energy Data Book (EERE)

Building Type and System Type (Million SF) Total Education Food Sales Food Service Health Care Lodging Mercantile and Service Office Public Buildings WarehouseStorage Total...

Note: This page contains sample records for the topic "waste storage building" 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

Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year  

SciTech Connect

This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

1985-06-01T23:59:59.000Z

362

Activated aluminum hydride hydrogen storage compositions and...  

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

and Biofuels Building Energy Efficiency Electricity Transmission Energy Analysis Energy Storage Geothermal Hydrogen and Fuel Cell Hydropower, Wave and Tidal Industrial...

363

Y-12 Plant decontamination and decommissioning Technology Logic Diagram for Building 9201-4: Volume 3, Technology evaluation data sheets: Part B, Decontamination; robotics/automation; waste management  

SciTech Connect

This volume consists of the Technology Logic Diagrams (TLDs) for the decontamination, robotics/automation, and waste management areas.

NONE

1994-09-01T23:59:59.000Z

364

Thermal Storage with Conventional Cooling Systems  

E-Print Network (OSTI)

The newly opened Pennsylvania Convention Center in Philadelphia, PA; Exxon's Computer Facility at Florham Park, NJ; The Center Square Building in Philadelphia, are success stories for demand shifting through thermal storage. These buildings employ a...

Kieninger, R. T.

1994-01-01T23:59:59.000Z

365

Building 32 35 Building 36  

E-Print Network (OSTI)

Building 10 Building 13 Building 7 LinHall Drive Lot R10 Lot R12 Lot 207 Lot 209 LotR9 Lot 205 Lot 203 LotBuilding30 Richland Avenue 39 44 Building 32 35 Building 36 34 Building 18 Building 19 11 12 45 29 15 Building 5 8 9 17 Building 16 6 Building 31 Building 2 Ridges Auditorium Building 24 Building 4

Botte, Gerardine G.

366

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect

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

367

CFES RESEARCH THRUSTS: Energy Storage  

E-Print Network (OSTI)

CFES RESEARCH THRUSTS: Energy Storage Wind Energy Solar Energy Smart Grids Smart Buildings For our on their progress and findings Along with the research advances, sponsors will benefit from the visibility

Lü, James Jian-Qiang

368

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk  

SciTech Connect

Volume three contains appendices for the following: Public comments do DOE`s proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates.

NONE

1995-08-01T23:59:59.000Z

369

The largest radioactive waste glassification  

NLE Websites -- All DOE Office Websites (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

370

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect

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

371

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

372

Hanford Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule -  

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

Reaches Recovery Act Goal for Waste Cleanup Ahead of Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule - Workers Shipped 1,800 Cubic Meters for Treatment and Disposal Hanford Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule - Workers Shipped 1,800 Cubic Meters for Treatment and Disposal July 26, 2011 - 12:00pm Addthis Media Contacts Andre Armstrong, CH2M HILL Andre_L_Armstrong@rl.gov 509-376-6773 Geoff Tyree, DOE Geoffrey.Tyree@rl.doe.gov 509-376-4171 RICHLAND, Wash. - Today, the Department of Energy Hanford Site announced it reached a cleanup goal more than two months ahead of schedule at the Hanford Site in southeast Washington State. Supported by funding from the American Recovery and Reinvestment Act, workers retrieved containers of contaminated material from storage buildings and underground storage trenches and prepared them for treatment

373

Hanford Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule -  

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

Reaches Recovery Act Goal for Waste Cleanup Ahead of Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule - Workers Shipped 1,800 Cubic Meters for Treatment and Disposal Hanford Reaches Recovery Act Goal for Waste Cleanup Ahead of Schedule - Workers Shipped 1,800 Cubic Meters for Treatment and Disposal July 26, 2011 - 12:00pm Addthis Media Contacts Andre Armstrong, CH2M HILL Andre_L_Armstrong@rl.gov 509-376-6773 Geoff Tyree, DOE Geoffrey.Tyree@rl.doe.gov 509-376-4171 RICHLAND, Wash. - Today, the Department of Energy Hanford Site announced it reached a cleanup goal more than two months ahead of schedule at the Hanford Site in southeast Washington State. Supported by funding from the American Recovery and Reinvestment Act, workers retrieved containers of contaminated material from storage buildings and underground storage trenches and prepared them for treatment

374

Lab obtains approval to begin design on new radioactive waste...  

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

New radioactive waste staging facility Lab obtains approval to begin design on new radioactive waste staging facility The 4-acre complex will include multiple staging buildings...

375

Building Energy Software Tools Directory: Building Performance Compass  

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

Building Performance Compass Building Performance Compass Building Performance Compass logo Building Performance Compass analyzes commercial and multi-family building energy use patterns in a simple, easy-to-use Web-based interface. Using building details and energy data from the buildingÂ’s utility bills, it is unique in its ability to benchmark and compare all buildings, whether residential or commercial. Recent enhancements to Building Performance Compass include new multi-family support, the ability to track non-energy quantities such as water and waste, and features such as its fast-feedback report, which enables reporting energy savings as early as one month after work is completed. Building Performance Compass also provides extensive tracking of building data and usage, as well as the ability to upload and track

376

Basis for Section 3116 Determination for Salt Waste Disposal...  

Office of Environmental Management (EM)

gallons 1 2 (Mgal) of liquid radioactive waste stored in underground waste storage tanks at SRS. Much of this waste resulted from the reprocessing of spent nuclear fuel for...

377

Final Tank Closure and Waste Management Environmental Impact...  

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

and treat the waste remaining in 177 underground storage tanks; store the high-level radioactive waste (HLW); dispose of the low-activity waste (LAW) at the Hanford Site...

378

High-Yield Harvest of Nanofibers/Mesoporous Carbon Composite by Pyrolysis of Waste Biomass and Its Application for High Durability Electrochemical Energy Storage  

Science Journals Connector (OSTI)

Themochemically converting the waste biomass to functional carbon nanomaterials and bio-oil is an environmentally friendly apporach by reducing greenhouse gas emissions and air pollution caused by open burning. ...

Wu-Jun Liu; Ke Tian; Yan-Rong He; Hong Jiang; Han-Qing Yu

2014-11-05T23:59:59.000Z

379

Precipitation of cesium jointly with uranium from nitric acid liquid radioactive wastes to obtain solid matrices for long-term storage  

Science Journals Connector (OSTI)

The possibility of converting liquid radioactive wastes containing Cs into chemically and thermodynamically stable...4U5O17...can be prepared by different procedures. The resulting compounds are characterized by ...

Yu. I. Korneiko; A. A. Murzin; O. V. Shmidt

2009-08-01T23:59:59.000Z

380

Microbiological evaluation of the condition of cement compounds with radioactive wastes after long-term storage in near-surface repositories  

Science Journals Connector (OSTI)

Analysis of the core material taken by check drilling of a monolith of cemented radioactive waste in near-surface repositories operated for 15–45 years revealed the presence of damaged areas in the cement matr...

O. A. Gorbunova; A. S. Barinov

2012-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

Energy Storage | Open Energy Information  

Open Energy Info (EERE)

Storage Storage Jump to: navigation, search TODO: Source information Contents 1 Introduction 2 Benefits 3 Technologies 4 References Introduction Energy storage is a tool that can be used by grid operators to help regulate the electrical grid and help meet demand. In its most basic form, energy storage "stores" excess energy that would otherwise be wasted so that it can be used later when demand is higher. Energy Storage can be used to balance microgrids, perform frequency regulation, and provide more reliable power for high tech industrial facilities.[1] Energy storage will also allow for the expansion of intermittent renewable energy, like wind and solar, to provide electricity around the clock. Some of the major issues concerning energy storage include cost, efficiency, and size.

382

Technical requirements specification for tank waste retrieval  

SciTech Connect

This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

Lamberd, D.L.

1996-09-26T23:59:59.000Z

383

Waste to be Consolidated at I...  

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

reduce potential risks to human health and the environment associated with long-term waste storage. Designated federal, state and tribal officials can monitor the shipments. ...

384

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

385

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

386

Building Technologies Office: Residential Buildings  

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

Residential Buildings Residential Buildings to someone by E-mail Share Building Technologies Office: Residential Buildings on Facebook Tweet about Building Technologies Office: Residential Buildings on Twitter Bookmark Building Technologies Office: Residential Buildings on Google Bookmark Building Technologies Office: Residential Buildings on Delicious Rank Building Technologies Office: Residential Buildings on Digg Find More places to share Building Technologies Office: Residential Buildings on AddThis.com... About Take Action to Save Energy Partner With DOE Activities Technology Research, Standards, & Codes Popular Residential Links Success Stories Previous Next Warming Up to Pump Heat. Lighten Energy Loads with System Design. Cut Refrigerator Energy Use to Save Money. Tools EnergyPlus Whole Building Simulation Program

387

Ferrocyanide tank waste stability  

SciTech Connect

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

388

Derr Track Storage Bldg Sigma Alpha  

E-Print Network (OSTI)

!( Derr Track Storage Bldg Japan Center Memorial Bell Tower Solar House Primrose Chancellor & Storage Bio. Sci Avent Ferry Complex Building Sigma Phi Epsilon 7 Welch Pi Kappa Alpha 10 Sigma Alpha Mu 4 and Visitor's Center Thompson Admin II Bostian Library Storage Facility Winston Clark Ricks Robertson Harris

Reeves, Douglas S.

389

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

390

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

391

Robotic Inspection System for Bulk Liquid Storage Tanks  

E-Print Network (OSTI)

for aboveground storage tanks (ASTs) requires: drainage of the product; cleaning of the vessel with water or solvents; physical removal, collection and containment of petroleum and chemical waste residues, including the waste streams created by the cleaning...

Hartsell, D. R.; Hakes, K. J.

392

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

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

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

393

Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley Low-Level Waste Collection and Transfer System upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory  

SciTech Connect

This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements. Portions of the LLW system are several decades old, or older, and do not comply with current environmental protection regulations. Several subsystems of the LLW system have been designated to receive a state-of-the-art replacement and refurbishment. One such subsystem serves Building 2026, the High Radiation Level Analytical Laboratory. This assessment focuses on the scope of work for the Building 2026 replacement LLW Collection and Transfer System, including the provision of a new Monitoring and Control Station (Building 2099) to receive, store, and treat (adjust pH) low level radioactive waste.

Not Available

1994-10-01T23:59:59.000Z

394

Evaluation of the Technical Basis for Extended Dry Storage and  

E-Print Network (OSTI)

-- Executive Summary U.S. Nuclear Waste Technical Review Board December 2010 #12;U.S.U.S. Nuclear Waste Technical Review Board Authors This report was prepared for the U.S. Nuclear Waste Technical Review Board.NWTRB.GOV ii #12;Extended Dry Storage and Transportation of Used Nuclear Fuel U.S. Nuclear Waste Technical

395

Building stability through decentralization : the environmental, economic, and ethical argument for informal sector collection and decentralized waste processing in urban India  

E-Print Network (OSTI)

Rapid population growth, urbanization and increasing affluence have led to increases in consumption and waste generation in all Indian cities. The current system, a mix of informal recyclables collection and centralized ...

Howe, Caroline Louise

2014-01-01T23:59:59.000Z

396

E-Print Network 3.0 - aqueous tank waste Sample Search Results  

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

Summary: by tank truck. The various wastes, when received, are pumped to storage tanks, then blended to produce... of Liquid Fluid Wastes General Description Light...

397

The Ethics of Nuclear Waste in Canada: Risks, Harms and Unfairness.  

E-Print Network (OSTI)

??The Nuclear Waste Management Organization (NWMO)  – the crown corporation responsible for the long-term storage of nuclear fuel waste in Canada  – seeks to bury… (more)

Wilding, Ethan

2010-01-01T23:59:59.000Z

398

Mixed waste characterization reference document  

SciTech Connect

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

399

Buildings*","Principal Building Activity"  

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

3. Selected Principal Activity: Part 2, Number of Buildings for Non-Mall Buildings, 2003" 3. Selected Principal Activity: Part 2, Number of Buildings for Non-Mall Buildings, 2003" ,"Number of Buildings (thousand)" ,"All Buildings*","Principal Building Activity" ,,"Office","Public Assembly","Public Order and Safety","Religious Worship","Service","Warehouse and Storage" "All Buildings* ...............",4645,824,277,71,370,622,597 "Building Floorspace" "(Square Feet)" "1,001 to 5,000 ...............",2552,503,119,37,152,434,294 "5,001 to 10,000 ..............",889,127,67,"Q",104,100,110 "10,001 to 25,000 .............",738,116,69,"Q",83,66,130 "25,001 to 50,000 .............",241,43,9,"Q",27,17,27

400

1999 Commercial Buildings Characteristics--Disaggregated Principal Building  

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

Disaggregated Principal Building Activities Disaggregated Principal Building Activities Disaggregated Principal Building Activities The 1999 CBECS collected information for 20 general building activities. Five of the activities were aggregated and data for 16 activities are displayed in the detailed tables. Within the aggregated warehouse and storage category, nonrefrigerated warehouses greatly exceeded refrigerated warehouses both in amount of floorspace and number of buildings (compare Figure 1 with Figure 2). Within the mercantile category, the number of retail buildings greatly exceeded strip shopping buildings which, in turn, greatly exceeded enclosed shopping malls (Figure 2). The amount of mercantile floorspace was more evenly distributed (Figure 1) because of differences in average building size-enclosed malls were largest and retail buildings the smallest.

Note: This page contains sample records for the topic "waste storage building" 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

Solid waste retrieval. Phase 1, Operational basis  

SciTech Connect

This Document describes the operational requirements, procedures, and options for execution of the retrieval of the waste containers placed in buried storage in Burial Ground 218W-4C, Trench 04 as TRU waste or suspect TRU waste under the activity levels defining this waste in effect at the time of placement. Trench 04 in Burial Ground 218W-4C is totally dedicated to storage of retrievable TRU waste containers or retrievable suspect TRU waste containers and has not been used for any other purpose.

Johnson, D.M.

1994-09-30T23:59:59.000Z

402

Simulation of thermal stress influence on the Boom Clay kerogen (Oligocene, Belgium) in relation to long-term storage of high activity nuclear waste: I. Study of generated soluble compounds  

Science Journals Connector (OSTI)

Closed pyrolyses were performed on the Boom Clay kerogen to simulate the weak thermal stress applied during the in situ CERBERUS heating experiment (80 °C for 5 a). Two stronger thermal stresses, encompassing the range generally considered for the long-term disposal of high-activity nuclear waste (80 °C for 1 ka and 120 °C for 3 ka), were also simulated. Quantitative and qualitative studies were carried out on the products thus generated with a focus on the C12+ fraction, especially on its polar components. It thus appeared that the soluble C12+ fractions generated during these simulation experiments comprise a wide variety of polar O- and/or N-containing compounds, including carboxylic acids and phenols. The nature and/or the relative abundance of these polar compounds exhibit strong variations, with the extent of the thermal stress, reflecting the primary cracking of different types of structures with different thermal stability and the occurrence of secondary degradation reactions. These observations support the idea that the compounds, generated upon exposure of the Boom Clay kerogen to a low to moderate thermal stress, may affect the effectiveness of the geological barrier upon long-term storage of high-activity nuclear waste.

I. Deniau; S. Derenne; C. Beaucaire; H. Pitsch; C. Largeau

2005-01-01T23:59:59.000Z

403

BETTER BUILDINGS ALLIANCE  

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

Commercial buildings—our offices, schools, hospitals, restaurants, hotels and stores—consume nearly 20% of all energy used in the United States. We spend more than $200 billion each year to power our country's commercial buildings. Unfortunately, much of this energy and money is wasted; a typical commercial building could save 20% on its energy bills simply by commissioning existing systems so they operate as intended. Energy efficiency is a cost-effective way to save money, support job growth, reduce pollution, and improve competitiveness.

404

Technical basis for performance goals, design requirements, and material recommendations for the NNWSI [Nevada Nuclear Waste Storage Investigations] Repository Sealing Program  

SciTech Connect

The objectives are to develop performance goals, to assess the need for seals, to define design requirements, and to recommend potential sealing materials for the sealing system. Performance goals are the allowable amounts of water that can enter the waste disposal areas directly from the rock mass above the repository and indirectly from shafts and ramps connecting to the underground facility. These goals are developed using a numerical model that calculates radionuclide releases. To determine the need for sealing, estimates of water flow into shafts, ramps, and the underground facility under anticipated conditions are developed and are compared with the performance goals. It is concluded that limited sealing measures, such as emplacement of shaft fill, are sufficient to properly isolate the radioactive waste in the repository. A broad range of sealing design options and associated hydrologic design requirements are proposed to provide a greater degree of assurance that the hydrologic performance goals can be met even if unanticipated hydrologic flows enter the waste disposal areas. The hydrologic design requirements are specific, hydraulic conductivity values selected for specific, seal design options to achieve the performance goals. Using these hydrologic design requirements and additional design requirements, preferred materials are identified for continued design and laboratory analyses. In arriving at these preferred materials, results from previous laboratory testing are briefly discussed. 96 refs., 48 figs., 28 tabs.

Fernandez, J.A.; Kelsall, P.C.; Case, J.B.; Meyer, D.

1987-09-01T23:59:59.000Z

405

Building Energy Software Tools Directory: Building Energy Analyzer  

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

Building Energy Analyzer Building Energy Analyzer Building Energy Analyzer logo. Provides quick economic analysis for commercial and industrial buildings. Building Energy Analyzer (BEA) estimates annual and monthly loads and costs associated with air-conditioning, heating, on-site power generation, thermal storage, and heat recovery systems for a given building and location. The user can compare the performance of standard and high efficiency electric chillers, variable speed electric chillers, absorption chillers, engine chillers, thermal storage, on-site generators, heat recovery, or desiccant systems. The user can also prepare side-by-side economic comparisons of different energy options and equipment life cycle cost analysis. The BEA is a system screening tool. It is a tool that is

406

Hazardous Wastes Management (Alabama) | Department of Energy  

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

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

407

UNBC Hazardous Waste Guide Proper waste management practices are essential for the safety of all students, staff, and  

E-Print Network (OSTI)

treatment of hazardous waste can also cause long-term environmental effects, such as contaminated ground by the Radiation Safety Officer. #12;Storage of Waste Each lab must decide on an appropriate location for wasteUNBC Hazardous Waste Guide Proper waste management practices are essential for the safety of all

Northern British Columbia, University of

408

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT  

SciTech Connect

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

409

SRS - Programs - Waste Solidification  

NLE Websites -- All DOE Office Websites (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

410

buildings | OpenEI  

Open Energy Info (EERE)

buildings buildings Dataset Summary Description Emissions from energy use in buildings are usually estimated on an annual basis using annual average multipliers. Using annual numbers provides a reasonable estimation of emissions, but it provides no indication of the temporal nature of the emissions. Therefore, there is no way of understanding the impact on emissions from load shifting and peak shaving technologies such as thermal energy storage, on-site renewable energy, and demand control. Source NREL Date Released April 11th, 2011 (3 years ago) Date Updated April 11th, 2011 (3 years ago) Keywords buildings carbon dioxide emissions carbon footprinting CO2 commercial buildings electricity emission factors ERCOT hourly emission factors interconnect nitrogen oxides NOx SO2

411

Environmental impacts of proposed Monitored Retrievable Storage  

SciTech Connect

This report describes environmental impacts from a proposed monitored retrievable storage facility for spent fuels to be located in Tennessee. Areas investigated include: water supply, ground water, air quality, solid waste management, and health hazards. (CBS)

Not Available

1985-12-17T23:59:59.000Z

412

Encouraging Combined Heat and Power in California Buildings  

E-Print Network (OSTI)

incentive ($/W) wind turbine waste heat to power pressurewind turbines, fuel cells, organic rankine cycle/waste heat capture, pressure reduction turbines, advanced energy storage, and combined heat and power

Stadler, Michael

2014-01-01T23:59:59.000Z

413

Waste Isolation Pilot Plant 2003 Site Environmental Report  

SciTech Connect

The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management, defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated storage rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. Salt under pressure is relatively plastic, and mine openings will be allowed to creep closed for final disposal, encapsulating and isolating the waste.

Washington Regulatory and Environmental Services

2005-09-03T23:59:59.000Z

414

NETL: Carbon Storage - Geologic Storage  

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

Geologic Storage Geologic Storage Carbon Storage Geologic Storage Focus Area Geologiccarbon dioxide (CO2) storage involves the injection of supercritical CO2 into deep geologic formations (injection zones) overlain by competent sealing formations and geologic traps that will prevent the CO2 from escaping. Current research and field studies are focused on developing better understanding 11 major types of geologic storage reservoir classes, each having their own unique opportunities and challenges. Understanding these different storage classes provides insight into how the systems influence fluids flow within these systems today, and how CO2 in geologic storage would be anticipated to flow in the future. The different storage formation classes include: deltaic, coal/shale, fluvial, alluvial, strandplain, turbidite, eolian, lacustrine, clastic shelf, carbonate shallow shelf, and reef. Basaltic interflow zones are also being considered as potential reservoirs. These storage reservoirs contain fluids that may include natural gas, oil, or saline water; any of which may impact CO2 storage differently. The following summarizes the potential for storage and the challenges related to CO2 storage capability for fluids that may be present in more conventional clastic and carbonate reservoirs (saline water, and oil and gas), as well as unconventional reservoirs (unmineable coal seams, organic-rich shales, and basalts):

415

Fact Sheet: Grid-Scale Flywheel Energy Storage Plant | Department...  

Office of Environmental Management (EM)

Fact Sheet: Grid-Scale Flywheel Energy Storage Plant Fact Sheet: Grid-Scale Flywheel Energy Storage Plant Beacon Power will design, build, and operate a utility-scale 20 MW...

416

Building Design | Department of Energy  

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

Design Design Building Design As a researcher at the Pacific Northwest National Laboratory, Dr. Michael Brambley is working to improve the energy efficiency of our nation’s buildings. In this "10 Questions," learn how he is marrying engineering and computer technology to cut energy waste in commercial buildings. As a researcher at the Pacific Northwest National Laboratory, Dr. Michael Brambley is working to improve the energy efficiency of our nation's buildings. In this "10 Questions," learn how he is marrying engineering and computer technology to cut energy waste in commercial buildings. Commercial buildings have high energy needs and can put great strain on the nation's power grids during peak periods. Developing more efficient

417

Autonomous Hazardous Waste Inspection Vehicle Eric Byler, Wendell Chun, William Hoff, Dan Layne  

E-Print Network (OSTI)

Engineering Laboratory, and Rocky Flats Plant). 1.1 Problem Most waste storage facilities contain 5,000 to 20

Hoff, William A.

418

Buildings Energy Data Book  

Buildings Energy Data Book (EERE)

1.1 Buildings Sector Energy Consumption 1.1 Buildings Sector Energy Consumption 1.2 Building Sector Expenditures 1.3 Value of Construction and Research 1.4 Environmental Data 1.5 Generic Fuel Quad and Comparison 1.6 Embodied Energy of Building Assemblies 2The Residential Sector 3Commercial Sector 4Federal Sector 5Envelope and Equipment 6Energy Supply 7Laws, Energy Codes, and Standards 8Water 9Market Transformation Glossary Acronyms and Initialisms Technology Descriptions Building Descriptions Other Data Books Biomass Energy Transportation Energy Power Technologies Hydrogen Download the Entire Book Skip down to the tables Chapter 1 provides an overview of energy use in the U.S. buildings sector, which includes single- and multi-family residences and commercial buildings. Commercial buildings include offices, stores, restaurants, warehouses, other buildings used for commercial purposes, and government buildings. Section 1.1 presents data on primary energy consumption, as well as energy consumption by end use. Section 1.2 focuses on energy and fuel expenditures in U.S. buildings. Section 1.3 provides estimates of construction spending, R&D, and construction industry employment. Section 1.4 covers emissions from energy use in buildings, construction waste, and other environmental impacts. Section 1.5 discusses key measures used throughout the Data Book, such as a quad, primary versus delivered energy, and carbon emissions. Section 1.6 provides estimates of embodied energy for various commercial building assemblies. The main points from this chapter are summarized below:

419

Electricity cost saving comparison due to tariff change and ice thermal storage (ITS) usage based on a hybrid centrifugal-ITS system for buildings: A university district cooling perspective  

Science Journals Connector (OSTI)

Abstract In this paper, the case study of a district cooling system of a university located in a South East Asia region (lat: 01°29?; long: 110°20?E) is presented. In general, the university has high peak ambient temperature of around 32–35 °C coupled with high humidity of about 85% during afternoon period. The total electricity charge for the Universiti Malaysia Sarawak Campus is very high amounting to more than $314,911 per month. In this paper, a few district cooling schemes are investigated to provide “what-if analysis” and in order to minimize the overall electricity charges. Few scenarios designed for the application of centrifugal with and without ice-thermal storage (ITS) systems on the buildings were investigated. It was found that, due to the local tariff status, marginally saving can be achieved in the range of 0.08–3.13% if a new tariff is adopted; and a total of further saving of 1.26–2.43% if ITS is operated. This marginally saving is mainly due to the local tariff conditions and lower local temperature range (?T) which are less favorable as compared with those reported in the literature elsewhere.

Mohammad Omar Abdullah; Lim Pai Yii; Ervina Junaidi; Ghazali Tambi; Mohd Asrul Mustapha

2013-01-01T23:59:59.000Z

420

Building Technologies Office: Commercial Building Research and Development  

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

Research and Development Research and Development Photo of NREL researcher Jeff Tomberlin working on a data acquisition panel at the Building Efficiency Data Acquisition and Control Laboratory at NREL's Thermal Test Facility. The Building Technology Program funds research that can dramatically improve energy efficiency in commercial buildings. Credit: Dennis Schroeder, NREL PIX 20181 The Building Technologies Office (BTO) invests in technology research and development activities that can dramatically reduce energy consumption and energy waste in buildings. Buildings in the United States use nearly 40 quadrillion British thermal units (Btu) of energy for space heating and cooling, lighting, and appliances, an amount equivalent to the annual amount of electricity delivered by more than 3,800 500-megawatt coal-fired power plants. The BTO technology portfolio aims to help reduce building energy requirements by 50% through the use of improved appliances; windows, walls, and roofs; space heating and cooling; lighting; and whole building design strategies.

Note: This page contains sample records for the topic "waste storage building" 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

Hydrogen storage and supply system - Energy Innovation Portal  

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

and Biofuels Building Energy Efficiency Electricity Transmission Energy Analysis Energy Storage Geothermal Hydrogen and Fuel Cell Hydropower, Wave and Tidal Industrial...

422

Cryogenic Capable High Pressure Containers for Compact Storage...  

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

and Biofuels Building Energy Efficiency Electricity Transmission Energy Analysis Energy Storage Geothermal Hydrogen and Fuel Cell Hydropower, Wave and Tidal Industrial...

423

Building Technologies Office: Building America: Bringing Building  

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

America: Bringing Building Innovations to Market America: Bringing Building Innovations to Market Building America logo The U.S. Department of Energy's (DOE) Building America program has been a source of innovations in residential building energy performance, durability, quality, affordability, and comfort for more than 15 years. This world-class research program partners with industry (including many of the top U.S. home builders) to bring cutting-edge innovations and resources to market. For example, the Solution Center provides expert building science information for building professionals looking to gain a competitive advantage by delivering high performance homes. At Building America meetings, researchers and industry partners can gather to generate new ideas for improving energy efficiency of homes. And, Building America research teams and DOE national laboratories offer the building industry specialized expertise and new insights from the latest research projects.

424

Salt Waste Processing Facility Fact Sheet | Department of Energy  

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

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications EIS-0082-S2: Amended Record of Decision Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report EIS-0082-S2: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)

425

324 Facility special-case waste assessment in support of 324 closure (TPA milestone M-89-05)  

SciTech Connect

Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05, requires US Department of Energy, Richland Operations Office to complete a 324 Facility Special-Case Waste Assessment in Support of 324 Closure. This document, HNF-1270, has been prepared with the intent of meeting this regulatory commitment. Alternatives for the special-case wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.

Hobart, R.L.

1998-06-25T23:59:59.000Z

426

Interim Storage Facility decommissioning. Final report  

SciTech Connect

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel.

Johnson, R.P.; Speed, D.L.

1985-03-15T23:59:59.000Z

427

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

SciTech Connect

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

428

State of Tennessee Hazardous Waste Management Permit, TNHW-127  

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

Class 1 1 Modification, Dated: 10/20/06 TABLE OF CONTENTS U.S. DEPARTMENT OF ENERGY, Y-12 NATIONAL SECURITY COMPLEX OAK RIDGE, TENNESSEE HAZARDOUS WASTE CONTAINER STORAGE AND TREATMENT UNITS BUILDINGS 9206, 9212, 9720-12, 9811-9, AND 9812 AND THE ORGANIC HANDLING UNIT EPA ID NUMBER: TN3 89 009 0001 Page Number I. STANDARD CONDITIONS A. EFFECT OF PERMIT I-1 B. SEVERABILITY I-1 C. DEFINITIONS I-2 D. GENERAL DUTIES AND REQUIREMENTS I-4 E. CONFIDENTIAL INFORMATION I-10 F. DOCUMENTS TO BE MAINTAINED AT THE FACILITY I-10 G. ANNUAL MAINTENANCE FEE I-10 H. REQUIRED NOTICES I-10 I. ORDER OF PRECEDENCE I-11 J. PERMIT STRUCTURE I-11 II. GENERAL FACILITY CONDITIONS A. HAZARDOUS WASTES TO BE MANAGED II-1 B. MAINTENANCE OF THE FACILITY II-1

429

State of Tennessee Hazardous Waste Management Permit, TNHW-122  

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

Class 1 1 Modification, Dated: 12/18/06 TABLE OF CONTENTS U.S. DEPARTMENT OF ENERGY, Y-12 NATIONAL SECURITY COMPLEX OAK RIDGE, TENNESSEE HAZARDOUS WASTE CONTAINER STORAGE AND TREATMENT UNITS BUILDINGS 9720-9, 9720-25, AND 9720-31 EPA ID NUMBER: TN3 89 009 0001 Page Number I. STANDARD CONDITIONS A. EFFECT OF PERMIT I-1 B. SEVERABILITY I-1 C. DEFINITIONS I-2 D. GENERAL DUTIES AND REQUIREMENTS I-4 E. CONFIDENTIAL INFORMATION I-10 F. DOCUMENTS TO BE MAINTAINED AT THE FACILITY I-10 G. ANNUAL MAINTENANCE FEE I-10 H. REQUIRED NOTICES I-10 I. ORDER OF PRECEDENCE I-11 J. PERMIT STRUCTURE I-11 II. GENERAL FACILITY CONDITIONS A. HAZARDOUS WASTES TO BE MANAGED II-1 B. MAINTENANCE OF THE FACILITY II-1 C. SAMPLING, ANALYSIS, AND MONITORING II-1

430

Residential Buildings  

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

Apartment building exterior and interior Apartment building exterior and interior Residential Buildings EETD's research in residential buildings addresses problems associated with whole-building integration involving modeling, measurement, design, and operation. Areas of research include the movement of air and associated penalties involving distribution of pollutants, energy and fresh air. Contacts Max Sherman MHSherman@lbl.gov (510) 486-4022 Iain Walker ISWalker@lbl.gov (510) 486-4692 Links Residential Building Systems Group Batteries and Fuel Cells Buildings Energy Efficiency Applications Commercial Buildings Cool Roofs and Heat Islands Demand Response Energy Efficiency Program and Market Trends High Technology and Industrial Systems Lighting Systems Residential Buildings Simulation Tools Sustainable Federal Operations

431

Using Building Simulation and Optimization to Calculate Lookup Tables for Control  

E-Print Network (OSTI)

building e?ciency. Thermal energy storage is becoming morestored in a strati?ed thermal energy storage (TES) tank andwith thermal storage. ACEEE Summer Study on Energy E?ciency

Coffey, Brian

2012-01-01T23:59:59.000Z

432

International Energy Agency Implementing Agreements and Annexes: A Guide for Building Technologies Program Managers  

E-Print Network (OSTI)

develop advanced storage concepts for solar and low energyAnnex 32, Advanced Storage Concepts for Solar and Low EnergyAdvanced storage concepts for solar and low energy buildings

Evans, Meredydd

2008-01-01T23:59:59.000Z

433

Memorandum of Understanding between US Department of Energy and the Public Agency for Radioactive Waste Management of the Republic of Hungary  

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

between The Department of Energy of the United States of America and The Public Agency for Radioactive Waste Management of the Republic of Hungary for Information Exchange Relating to Operation of Modular Vault Systems for Storage of Spent Nuclear Fuel 1. Participants The United States Department of Energy (DOE), a Participant to this Memorandum of Understanding (Memorandum), is the agency responsible for the management of radioactive wastes produced by or in the possession of tla U.S. Government (&mmercial reactor nuclear waste excluded) within the United Stztes, including spent nuclear fuel (SNF). DOE is the owner, operator, and licensee of the Fort St. Vrain (FSV) MVDS and the Hanford Canister Storage Building (CSB). DOE's Idaho Operations Office (DOE-

434

Energy Storage  

SciTech Connect

ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

Paranthaman, Parans

2014-06-03T23:59:59.000Z

435

Energy Storage  

ScienceCinema (OSTI)

ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

Paranthaman, Parans

2014-06-23T23:59:59.000Z

436

Food waste within food supply chains: quantification and potential for change to 2050  

Science Journals Connector (OSTI)

...potential for food waste reduction Interviewees...potential for food waste reduction. In developing...skills and knowledge, storage, transport and distribution...Kader 2005). For long-term sustainability...approaches to food waste reduction include...labelling and food storage also have food waste...

2010-01-01T23:59:59.000Z

437

Property:Buildings/ModelBuildingType | Open Energy Information  

Open Energy Info (EERE)

Buildings/ModelBuildingType Buildings/ModelBuildingType Jump to: navigation, search This is a property of type Page. It links to pages that use the form Buildings Model. Education Food Sales Food Service Health Care (Inpatient) Health Care (Outpatient) Lodging Mercantile (Retail Other Than Mall) Mercantile (Enclosed and Strip Malls) Office Public Assembly Public Order and Safety Religious Worship Service Warehouse and Storage Other Vacant Pages using the property "Buildings/ModelBuildingType" Showing 12 pages using this property. G General Merchandise 2009 TSD Chicago High Plug Load 50% Energy Savings + Mercantile (Retail Other Than Mall) + General Merchandise 2009 TSD Chicago High Plug Load Baseline + Mercantile (Retail Other Than Mall) + General Merchandise 2009 TSD Chicago Low Plug Load 50% Energy Savings + Mercantile (Retail Other Than Mall) +

438

Waste Inspection Tomography (WIT)  

SciTech Connect

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

439

Rainwater Harvesting: Soil Storage and Infiltration System  

E-Print Network (OSTI)

A soil storage and infiltration system collects rainfall runoff from the roofs of buildings and directs it underground where it infiltrates the soil. Such a system conserves water and protects it from surface pollution. This publication describes...

Mechell, Justin; Lesikar, Bruce J.

2008-08-11T23:59:59.000Z

440

Around Buildings  

E-Print Network (OSTI)

Around Buildings W h y startw i t h buildings and w o r k o u t wa r d ? For one, buildings are difficult t o a v o i d these

Treib, Marc

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage building" 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

BUILDING NAME HEYDON-LAURENCE BUILDING  

E-Print Network (OSTI)

'S BUILDING PHYSICS BUILDING BAXTER'S LODGE INSTITUTE BUILDING CONSERVATION WORKS R.D.WATT BUILDING MACLEAYBUILDING NAME HEYDON-LAURENCE BUILDING PHARMACY AND BANK BUILDING JOHN WOOLEY BUILDING OLD TEARCHER BUILDING THE QUARANGLE BADHAM BUILDING J.D. STEWART BUILDING BLACKBURN BUILDING MADSEN BUILDING STORE

Viglas, Anastasios

442

ENERGY STAR Building Upgrade Manual | ENERGY STAR Buildings & Plants  

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

ENERGY STAR Building Upgrade Manual ENERGY STAR Building Upgrade Manual Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section Learn the benefits Get started Use Portfolio Manager Save energy Stamp out energy waste Find cost-effective investments Engage occupants Purchase energy-saving products Put computers to sleep Get help from an expert Take a comprehensive approach

443

Education Buildings  

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

Education Education Characteristics by Activity... Education Education buildings are buildings used for academic or technical classroom instruction, such as elementary, middle, or high schools, and classroom buildings on college or university campuses. Basic Characteristics [ See also: Equipment | Activity Subcategories | Energy Use ] Education Buildings... Seventy percent of education buildings were part of a multibuilding campus. Education buildings in the South and West were smaller, on average, than those in the Northeast and Midwest. Almost two-thirds of education buildings were government owned, and of these, over three-fourths were owned by a local government. Tables: Buildings and Size Data by Basic Characteristics Establishment, Employment, and Age Data by Characteristics

444

Lodging Buildings  

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

buildings. Since they comprised 7 percent of commercial floorspace, this means that their energy intensity was slightly above average. Lodging buildings were one of the few...

445

Using Dashboards to Improve Energy and Comfort in Federal Buildings  

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

Using Dashboards to Improve Energy and Comfort in Federal Buildings Using Dashboards to Improve Energy and Comfort in Federal Buildings Title Using Dashboards to Improve Energy and Comfort in Federal Buildings Publication Type Report LBNL Report Number LBNL-4283E Year of Publication 2011 Authors Marini, Kyle, Girish Ghatikar, and Richard C. Diamond Call Number LBNL-4283E Keywords commercial buildings, dashboards, energy, feedback, monitoring Abstract Federal agencies are taking many steps to improve the sustainability of their operations, including improving the energy efficiency of their buildings, promoting recycling and reuse of materials, encouraging carpooling and alternative transit schemes, and installing low flow water fixture units are just a few of the common examples. However, an often overlooked means of energy savings is to provide feedback to building users about their energy use through information dashboards connected to a building's energy information system.An Energy Information System (EIS), broadly defined, is a package of performance monitoring software, data acquisition hardware, and communication systems that is used to collect, store, analyze, and display energy information. At a minimum, the EIS provides the whole-building energy-use information (Granderson 2009a). We define a "dashboard" as a display and visualization tool that utilizes the EIS data and technology to provide critical information to users. This information can lead to actions resulting in energy savings, comfort improvements, efficient operations, and more. The tools to report analyzed information have existed in the information technology as business intelligence (Few 2006). The dashboard is distinguished from the EIS as a whole, which includes additional hardware and software components to collect and storage data, and analysis for resources and energy management (Granderson 2009b). EIS can be used for a variety of uses, including benchmarking, base-lining, anomaly detection, off-hours energy use evaluation, load shape optimization, energy rate analysis, retrofit and retro-commissioning savings (Granderson 2009a). The use of these EIS features depends on the specific users. For example, federal and other building managers may use anomaly detection to identify energy waste in a specific building, or to benchmark energy use in similar buildings to identify energy saving potential and reduce operational cost. There are several vendors of EIS technology that provide information on energy and other environmental variables in buildings.

446

Salt Waste Processing Facility Fact Sheet | Department of Energy  

Office of Environmental Management (EM)

waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications...

447

Chapter 8: Constructing the Building  

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

: : Constructing the Building Developing a Construction Plan Writing Effective Construction Documents Safeguarding Design Goals During Construction Protecting the Site Low-Impact Construction Processes Protecting Indoor Air Quality Managing Construction Waste LANL | Chapter 8 Constructing the Building Developing a Construction Plan A high-performance design is a great achievement, but it doesn't mean much if the building isn't then built as intended. Getting from design to a completed project happens in two stages: 1) development of construction documents and 2) actual construction. To successfully implement a sustainable design, the construction docu- ments must accurately convey the specifics that deter- mine building performance, and they have to set up

448

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

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

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

449

Tank Closure and Waste Management Environmental Impact Statement...  

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

from off site, while others suggested that the Final Waste Management Programmatic Environmental Impact Statement for Managing Treatment, Storage, and Disposal of Radioactive and...

450

Nuclear waste, public information and residential property values  

SciTech Connect

This document presents details about how increased public knowledge of high-level radioactive waste storage facilities effects the price of near-by residential properties.

Clark, E.E. [Marquette Univ., Milwaukee, WI (United States). Dept. of Economics]|[Argonne National Lab., IL (United States); Allison, T. [Argonne National Lab., IL (United States)

1995-10-10T23:59:59.000Z

451

Shipping Radioactive Waste by Rail from Brookhaven National Laboratory...  

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

Documents & Publications West Valley Demonstration Project Low-Level Waste Shipment Nuclear Fuel Storage and Transportation Planning Project Overview Prairie Island Indian...