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


1

The Simplicity Device: Your Personal Mobile Representative  

E-Print Network [OSTI]

The Simplicity Device: Your Personal Mobile Representative Giovanni Bartolomeo1, Francesca Martire1 mobile phone that stores and handles personal information about the user. The Simplicity Device can be connected (e.g. via Bluetooth) to several other devices thus allowing personalization of services

2

Processing and waste disposal representative for fusion breeder blanket systems  

SciTech Connect (OSTI)

This study is an evaluation of the waste handling concepts applicable to fusion breeder systems. Its goal is to determine if breeder blanket waste can be disposed of in shallow land burial, the least restrictive method under US Nuclear Regulatory regulations. The radionuclides expected in the materials used in fusion reactor blankets are described, as are plans for reprocessing and disposal of the components of different breeder blankets. An estimate of the operating costs involved in waste disposal is made.

Finn, P.A.; Vogler, S.

1987-01-01T23:59:59.000Z

3

Disposable rabbit  

DOE Patents [OSTI]

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

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

1986-01-01T23:59:59.000Z

4

Disposal rabbit  

DOE Patents [OSTI]

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

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

1983-10-12T23:59:59.000Z

5

MATERIAL HANDLING, STORAGE, AND DISPOSAL  

E-Print Network [OSTI]

Materials shall be stored in a manner that allows easy identification and access to labels, identification entering storage areas. All persons shall be in a safe position while materials are being loadedEM 385-1-1 XX Jun 13 14-1 SECTION 14 MATERIAL HANDLING, STORAGE, AND DISPOSAL 14.A MATERIAL

US Army Corps of Engineers

6

Persons, imposters, and monsters  

E-Print Network [OSTI]

This dissertation is about person features, their representation and interpretation in natural language. I will argue that there are several ways in which person features can be represented and interpreted. Most importantly, ...

Podobryaev, Alexander

2014-01-01T23:59:59.000Z

7

Proof of Proper Solid Waste Disposal (West Virginia)  

Broader source: Energy.gov [DOE]

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

8

Waste Disposal (Illinois)  

Broader source: Energy.gov [DOE]

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

9

Department Safety Representatives Department Safety Representative  

E-Print Network [OSTI]

Department Safety Representatives Overview Department Safety Representative Program/Operations Guidance Document The Department Safety Representative (DSR) serves a very important role with implementation of safety, health, and environmental programs on campus. The role of the DSR is to assist

Pawlowski, Wojtek

10

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

11

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory Poultry Farm Daily Disposal Methods 0;Disposal: Science and Theory First Composter in Delaware · Delmarva was of the first daily composting · 120 in USA over next 10 years #12;Disposal: Science and Theory Composting Procedure · Mixture ­ 1 ½ to 2

Benson, Eric R.

12

Disposal of drilling fluids  

SciTech Connect (OSTI)

Prior to 1974 the disposal of drilling fluids was not considered to be much of an environmental problem. In the past, disposal of drilling fluids was accomplished in various ways such as spreading on oil field lease roads to stabilize the road surface and control dust, spreading in the base of depressions of sandy land areas to increase water retention, and leaving the fluid in the reserve pit to be covered on closure of the pit. In recent years, some states have become concerned over the indescriminate dumping of drilling fluids into pits or unauthorized locations and have developed specific regulations to alleviate the perceived deterioration of environmental and groundwater quality from uncontrolled disposal practices. The disposal of drilling fluids in Kansas is discussed along with a newer method or treatment in drilling fluid disposal.

Bryson, W.R.

1983-06-01T23:59:59.000Z

13

Facility Representative Program, Criteria & Review Approach Documents  

Broader source: Energy.gov [DOE]

This page provides Criteria Review and Approach Documents (CRADS) to assist Facility Representatives. Please submit your CRADS for posting by sending them to the HQ FR Program Manager. Please include the subject, date, and a contact person.

14

Representative Control Gates  

E-Print Network [OSTI]

& Integrated - Operationaly Certified As-Deployed Baseline Mission Analysis Risk, Cost, etc Tools & MethodsUnderstand Customer Identify Feasible Alternatives Final Design Disposal Management Decision - System Deployed Requirements Concept Definition Analysis & Evaluation Definition Flowdown Criteria & Priorities Peer Review MCR

Rhoads, James

15

RADIOACTIVE WASTE DISPOSAL IN GRANITE  

E-Print Network [OSTI]

RADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. WitherspoonRADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. Wither spoona repository site in granite are to evaluate the suitability

Witherspoon, P.A.

2010-01-01T23:59:59.000Z

16

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

17

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory · Opciones para la eliminación · ¿Qué compostaje durante brotes de enfermedades Lista de contenido #12;Disposal: Science and Theory "Ante un brote brotes de IIAP #12;Disposal: Science and Theory · En 2004, se despoblaron 100 millones de aves en todo el

Benson, Eric R.

18

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

19

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory · Las recomendaciones de campo se la espuma #12;Disposal: Science and Theory · Múltiples especies de aves pueden despoblarse con espuma cesación #12;Disposal: Science and Theory · Dentro de una especie, pueden existir variaciones ­ Los ánades

Benson, Eric R.

20

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory 0 20 40 60 80 100 Compostaje #12;Disposal: Science and Theory · Delmarva fue de las primeras granjas en realizar el compostaje de en EE.UU. en los próximos 10 años. Pionera en compostaje en Delaware #12;Disposal: Science and Theory

Benson, Eric R.

Note: This page contains sample records for the topic "representing disposable personal" 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

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

22

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

23

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

24

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

25

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

26

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

27

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

28

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

29

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

30

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

31

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory 2004 ­ Participación de Bud Malone y la espuma 2009 ­ Ninguna ventaja para el gas Breve historia de la espuma #12;Disposal: Science sistema de boquilla ¿Qué es la espuma? #12;Disposal: Science and Theory · La espuma puede incluir: ­ Una

Benson, Eric R.

32

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

33

Personal Genomics, Personalized Medicine,  

E-Print Network [OSTI]

Personal Genomics, Personalized Medicine, & YOU Carrie Iwema, PhD, MLS 21st May 2012 AAAS/Science Translational Medicine panel discussion; MLA 2012 #12;Timeline: Human Genome Sequence HSLS, U.Pitt 1995 2014 2000 2003 2007 2007 2010 Human Genome Draft Sequence Complete Human Reference Genome Individual Human

Napp, Nils

34

Hazardous Waste Disposal Sites (Iowa)  

Broader source: Energy.gov [DOE]

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

35

Low level tank waste disposal study  

SciTech Connect (OSTI)

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

Mullally, J.A.

1994-09-29T23:59:59.000Z

36

Waste disposal package  

DOE Patents [OSTI]

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

Smith, M.J.

1985-06-19T23:59:59.000Z

37

Radioactive waste disposal package  

DOE Patents [OSTI]

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

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

38

Oil field waste disposal costs at commercial disposal facilities  

SciTech Connect (OSTI)

The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

Veil, J.A.

1997-10-01T23:59:59.000Z

39

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

40

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

Note: This page contains sample records for the topic "representing disposable personal" 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

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

Disposal: Science and Theory #12;Disposal: Science and Theory · Se ubica el carretón con el enfriamiento Ventiladores de túnel de viento #12;Disposal: Science and Theory · Se estaciona el remolque en uno: Science and Theory · Se usa un equipo de dos personas para hacer funcionar el sistema: ­ Operario del

Benson, Eric R.

42

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

43

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network [OSTI]

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

Benson, Eric R.

44

Developing operating procedures for a low-level radioactive waste disposal facility  

SciTech Connect (OSTI)

This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

1993-10-01T23:59:59.000Z

45

Radioactive waste material disposal  

DOE Patents [OSTI]

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

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

1995-10-24T23:59:59.000Z

46

The incandescent disposal system  

SciTech Connect (OSTI)

The electrotechnology device being introduced to the low-level waste market is an Incandescent Disposal System (IDS) for volume reduction and vitrification. The process changes the composition of the waste material, usually long molecular chains, into simple molecules and elements. It renders the volume of low-level wastes to a manageable solid vitrified residue, carbon black, and a water discharge. The solid material, which has been vitrified if silica is introduced into the waste stream, is an ideal inert filler. The carbon black is non-leaching and is readily available for vitrification as it comes out of the IDS.

Smith, R.G.

1996-03-01T23:59:59.000Z

47

Radioactive waste material disposal  

DOE Patents [OSTI]

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

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

1995-01-01T23:59:59.000Z

48

STANDARD ADMINISTRATIVE PROCEDURE 21.01.10.M0.02 Disposal of Surplus or Excess Property  

E-Print Network [OSTI]

Management Manual, System Regulation 21.01.09. 2. DISPOSAL OF FEDERAL SURPLUS PERSONAL PROPERTY Unless property. Procedures and Responsibilities 1. GENERAL 1.1 The Federal Surplus Property Donation Program-consumable Federal surplus personal property and Federal excess personal property, other than scrap acquired

49

Radioactive mixed waste disposal  

SciTech Connect (OSTI)

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01T23:59:59.000Z

50

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network [OSTI]

radioactive products as regular trash. All packages must be free of contamination, radiation symbols2/07 WASTE DISPOSAL SECTION CORNELL UNIVERSITY PROCEDURE for DISPOSAL of RADIOACTIVE MATERIALS This procedure has been developed to ensure the safety of those individuals who handle radioactive waste

Pawlowski, Wojtek

51

Surveillance Guide - OSS 19.1 Personal Protective Equipment  

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

Date: Facility Representative RL Facility Representative Program May 23, 1995 Surveillance Guide OSS 19.1 Revision 0 Personal Protective Equipment Page 5 of 5...

52

Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3  

SciTech Connect (OSTI)

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

Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

2013-07-29T23:59:59.000Z

53

Title I Disposal Site  

E-Print Network [OSTI]

The Office of Legacy Management and the Navajo Nation have been discussing an item specified in the Long Term Surveillance Plan (LTSP) for the Mexican Hat site for some time now, and we have come to a resolution on the matter. The LTSP specifies seep sampling at the site to confirm that the disposal cell is operating as designed. Typically, this is to be done for a specific time and then reevaluated, but, in this LTSP there is no time frame given. After 8 years of experience in sampling and observing these six seeps, it has been found that most are not flowing at all, and those that have any water running are so limited in flow that it is difficult to obtain a sample. In addition, several risk assessments have been performed over the years to evaluate the possible ecological risks associated with exposure to this seep water. The analysis indicates there would be no eco-risk based on the historic data to any wildlife or livestock. This information and a full analysis of the situation was submitted to the Navajo Nation for their consideration, and, in further discussions, they have agreed to limit the sampling to only making observations during the annual cell inspection, and if water is observed to be increased compared to historic observations, then sampling will resume. Their agreement to this change is noted in the enclosed copy of their letter to DOE dated July 25, 2006. I have enclosed a copy of this report,

Mr. Bill; Von Till

2006-01-01T23:59:59.000Z

54

Transportation, Aging and Disposal Canister System Performance...  

Office of Environmental Management (EM)

specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. Transportation, Aging and Disposal Canister System Performance...

55

Chapter 37 Land Disposal Restrictions (Kentucky)  

Broader source: Energy.gov [DOE]

This administrative regulation establishes requirements for land disposal of hazardous waste. These include- surface impound exemptions, prohibitions on disposal and storage and treatment standards...

56

ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS...  

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

4: PROPERTY DISPOSAL RECORDS (Revision 2) ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) These records pertain to the sales by agencies of real and...

57

Solid Waste Disposal Facilities (Massachusetts)  

Broader source: Energy.gov [DOE]

These sections articulate rules for the maintenance and operation of solid waste disposal facilities, as well as site assignment procedures. Applications for site assignment will be reviewed by the...

58

Optimization of Waste Disposal - 13338  

SciTech Connect (OSTI)

From 2009 through 2011, remediation of areas of a former fuel cycle facility used for government contract work was conducted. Remediation efforts were focused on building demolition, underground pipeline removal, contaminated soil removal and removal of contaminated sediments from portions of an on-site stream. Prior to conducting the remediation field effort, planning and preparation for remediation (including strategic planning for waste characterization and disposal) was conducted during the design phase. During the remediation field effort, waste characterization and disposal practices were continuously reviewed and refined to optimize waste disposal practices. This paper discusses strategic planning for waste characterization and disposal that was employed in the design phase, and continuously reviewed and refined to optimize efficiency. (authors)

Shephard, E.; Walter, N.; Downey, H. [AMEC E and I, Inc., 511 Congress Street, Suite 200, Portland, ME 04101 (United States)] [AMEC E and I, Inc., 511 Congress Street, Suite 200, Portland, ME 04101 (United States); Collopy, P. [AMEC E and I, Inc., 9210 Sky Park Court, Suite 200, San Diego, CA 92123 (United States)] [AMEC E and I, Inc., 9210 Sky Park Court, Suite 200, San Diego, CA 92123 (United States); Conant, J. [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)] [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)

2013-07-01T23:59:59.000Z

59

Solid Waste Disposal Act (Texas)  

Broader source: Energy.gov [DOE]

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

60

Tank Waste Disposal Program redefinition  

SciTech Connect (OSTI)

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

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

1991-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Depleted uranium disposal options evaluation  

SciTech Connect (OSTI)

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

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

1994-05-01T23:59:59.000Z

62

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

E-Print Network [OSTI]

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

Slatton, Clint

63

Disposable telemetry cable deployment system  

DOE Patents [OSTI]

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

Holcomb, David Joseph (Sandia Park, NM)

2000-01-01T23:59:59.000Z

64

Wave represents displacement Wave represents pressure Source -Sound Waves  

E-Print Network [OSTI]

Wave represents displacement Wave represents pressure Source - Sound Waves Distance between crests is wavelength Number of crests passing a point in 1 second is frequency Wave represents pressure Target - Radio Waves Distance between crests is wavelength Number of crests passing a point in 1 second is frequency

Colorado at Boulder, University of

65

Optimizing High Level Waste Disposal  

SciTech Connect (OSTI)

If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being evaluated at Idaho National Laboratory and the facilities weve designed to evaluate options and support optimization.

Dirk Gombert

2005-09-01T23:59:59.000Z

66

Disposal of NORM waste in salt caverns  

SciTech Connect (OSTI)

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

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

1998-07-01T23:59:59.000Z

67

Deep Borehole Disposal Research: Demonstration Site Selection...  

Office of Environmental Management (EM)

Site Selection Guidelines, Borehole Seals Design, and RD&D Needs The U.S. Department of Energy has been investigating deep borehole disposal as one alternative for the disposal...

68

Spent Fuel Disposal Trust Fund (Maine)  

Broader source: Energy.gov [DOE]

Any licensee operating a nuclear power plant in this State shall establish a segregated Spent Nuclear Fuel Disposal Trust Fund in accordance with this subchapter for the eventual disposal of spent...

69

Dredged and Fill Material Disposal (North Dakota)  

Broader source: Energy.gov [DOE]

This chapter provides regulations for the disposal of dredged and fill material. Any entity desiring to dispose of such material must first obtain a permit, and the State Engineer has the...

70

Personal Property  

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

This Guide provides non-regulatory guidance and information to assist DOE organizations and contractors in implementing the DOE-wide and site-specific personal property management programs. It supplements the policy, requirements, and responsibilities information contained in the DOE Order cited above and clarifies the regulatory requirements contained in the Federal Property Management Regulation (FMR) and specific contracts.

2014-10-16T23:59:59.000Z

71

Waste disposal options report. Volume 1  

SciTech Connect (OSTI)

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

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

1998-02-01T23:59:59.000Z

72

Disposable remote zero headspace extractor  

DOE Patents [OSTI]

The remote zero headspace extractor uses a sampling container inside a stainless steel vessel to perform toxicity characteristics leaching procedure to analyze volatile organic compounds. The system uses an in line filter for ease of replacement. This eliminates cleaning and disassembly of the extractor. All connections are made with quick connect fittings which can be easily replaced. After use, the bag can be removed and disposed of, and a new sampling container is inserted for the next extraction.

Hand, Julie J. (Idaho Falls, ID); Roberts, Mark P. (Arco, ID)

2006-03-21T23:59:59.000Z

73

Sample storage/disposal study  

SciTech Connect (OSTI)

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

Valenzuela, B.D.

1994-09-29T23:59:59.000Z

74

Geosynthetic Clay Liner applications in waste disposal facilities  

SciTech Connect (OSTI)

Geosynthetic Clay Liners (GCLs) are becoming a popular alternative to compacted clay barrier layers, and represent the state of the art in waste disposal facility design. They possess many of the same qualities of compacted clay barrier layers while occupying only a small fraction of the airspace. This is a very attractive feature to waste disposal facility owners and operators. There are many manufacturers of GCLs in the marketplace, providing numerous products that can be used in a wide variety of applications. Designing for the constructing with a GCL an be a challenging task; stability issues must be evaluated, selecting the appropriate product should be considered, comprehensive specifications are needed to ensure proper product selection and installation, and steps must be taken during installation to prevent damage to the GCL. Perhaps most importantly, state regulatory agencies must be convinced that GCLs will provide long-term protection equivalent to a clay barrier layer. This paper will discuss design considerations, specification guidelines, installation criteria, construction quality assurance guidelines and regulatory issues pertaining to GCL. The paper will also present three brief case histories of relevant GCL applications in waste disposal facility design and construction. The purpose of the paper is to demonstrate that GCLs are a viable alternative to compacted clay barrier layers and to provide useful information in designing, specifying and installing them in waste disposal facilities.

McGrath, L.T.; Creamer, P.D. [RMT, Inc., Madison, WI (United States)

1995-12-31T23:59:59.000Z

75

BACHELOR THESIS The High Representative  

E-Print Network [OSTI]

BACHELOR THESIS The High Representative and the Libya Crisis An Assessment Dominique Prescher 8 and the Libya Crisis 2 Table of Content 1. Summary 4 2. Introduction 4 3. Theoretical Framework 8 3.1 Neo 34 9. Bibliography 36 #12;Bachelor Thesis The High Representative and the Libya Crisis 3 List

Vellekoop, Michel

76

Representative Albert R. Public Policy  

E-Print Network [OSTI]

billion to the authorization for the Low-Income Home Energy Assistance Program. He also successfully years as a member of the U.S. House of Representatives, representing Maryland's 4th Congressional District. During the last 12 years, he served on the powerful House Energy and Commerce Committee, most

Sibille, Etienne

77

Site characterization for LIL radioactive waste disposal in Romania  

SciTech Connect (OSTI)

Recent studies in radioactive waste management in Romania have focussed mainly on the disposal of low and intermediate level waste from the operation of the new nuclear power plant at Cernavoda. Following extensive geological, hydrological, seismological, physical and chemical investigations, a disposal site at Saligny has been selected. This paper presents description of the site at Saligny as well as the most important results of the site characterisation. These are reflected in the three-dimensional, stratigraphical representation of the loess and clay layers and in representative parameter values for the main layers. Based on these data, the simulation of the background, unsaturated-zone water flow at the Saligny site, calculated by the FEHM code, is in a good agreement with the measured moisture profile.

Diaconu, D. R. (Daniela R.); Birdsell, K. H. (Kay H.); Witkowski, M. S. (Marc S.)

2001-01-01T23:59:59.000Z

78

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis  

SciTech Connect (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energys mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-10-01T23:59:59.000Z

79

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER  

SciTech Connect (OSTI)

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

G. Radulesscu; J.S. Tang

2000-06-07T23:59:59.000Z

80

Aerosol can waste disposal device  

DOE Patents [OSTI]

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

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

1993-12-21T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Aerosol can waste disposal device  

DOE Patents [OSTI]

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

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

1993-01-01T23:59:59.000Z

82

Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.  

SciTech Connect (OSTI)

Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

2007-01-01T23:59:59.000Z

83

Electrochemical Apparatus with Disposable and Modifiable Parts  

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

in academia, might be able to afford only a limited inventory, which could stall productivity. Too expensive to be disposable, the cells must be cleaned after each experiment,...

84

WPCF Underground Injection Control Disposal Permit Evaluation...  

Open Energy Info (EERE)

and Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: WPCF Underground Injection Control Disposal Permit Evaluation and Fact Sheet Abstract...

85

Evaluation of exposure pathways to man from disposal of radioactive materials into sanitary sewer systems  

SciTech Connect (OSTI)

In accordance with 10 CFR 20, the US Nuclear Regulatory Commission (NRC) regulates licensees` discharges of small quantities of radioactive materials into sanitary sewer systems. This generic study was initiated to examine the potential radiological hazard to the public resulting from exposure to radionuclides in sewage sludge during its treatment and disposal. Eleven scenarios were developed to characterize potential exposures to radioactive materials during sewer system operations and sewage sludge treatment and disposal activities and during the extended time frame following sewage sludge disposal. Two sets of deterministic dose calculations were performed; one to evaluate potential doses based on the radionuclides and quantities associated with documented case histories of sewer system contamination and a second, somewhat more conservative set, based on theoretical discharges at the maximum allowable levels for a more comprehensive list of 63 radionuclides. The results of the stochastic uncertainty and sensitivity analysis were also used to develop a collective dose estimate. The collective doses for the various radionuclides and scenarios range from 0.4 person-rem for {sup 137}Cs in Scenario No. 5 (sludge incinerator effluent) to 420 person-rem for {sup 137}Cs in Scenario No. 3 (sewage treatment plant liquid effluent). None of the 22 scenario/radionuclide combinations considered have collective doses greater than 1000 person-rem/yr. However, the total collective dose from these 22 combinations was found to be about 2100 person-rem.

Kennedy, W.E. Jr.; Parkhurst, M.A.; Aaberg, R.L.; Rhoads, K.C.; Hill, R.L.; Martin, J.B. [Pacific Northwest Lab., Richland, WA (United States)

1992-05-01T23:59:59.000Z

86

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

E-Print Network [OSTI]

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

Machel, Hans

87

Minimizing WMinimizing WMinimizing WMinimizing WMinimizing Waste Disposal:aste Disposal:aste Disposal:aste Disposal:aste Disposal: Grass ClippingsGrass ClippingsGrass ClippingsGrass ClippingsGrass Clippings  

E-Print Network [OSTI]

Minimizing WMinimizing WMinimizing WMinimizing WMinimizing Waste Disposal:aste Disposal and supplying part of the fertilizer needs of the lawn. Adopt a mowing schedule to keep clippings short enough

Rainforth, Emma C.

88

Asset Management Equipment Disposal Form -Refrigerant Recovery  

E-Print Network [OSTI]

enters the waste stream with the charge intact (e.g., motor vehicle air conditioners, refrigeratorsAsset Management Equipment Disposal Form - Refrigerant Recovery Safe Disposal Requirements Under refrigeration, cold storage warehouse refrigeration, chillers, and industrial process refrigeration) has to have

Sin, Peter

89

September 1996 Personal Statement  

E-Print Network [OSTI]

the value of the personal statement as an indicator of writing ability. A Look at the Data The data showSeptember 1996 Personal Statement: A Writing Sample? Uses of the Personal Statement The personal to learn about an applicant's personal characteristics, to match interests between advisors and students

Chatterjee, Avik P.

90

A critical comparison of ten disposable cup LCAs  

SciTech Connect (OSTI)

Disposable cups can be made from conventional petro-plastics, bioplastics, or paperboard (coated with petro-plastics or bioplastics). This study compared ten life cycle assessment (LCA) studies of disposable cups with the aim to evaluate the robustness of their results. The selected studies have only one impact category in common, namely climate change with global warming potential (GWP) as its category indicator. Quantitative GWP results of the studies were closer examined. GWPs within and across each study show none of the cup materials to be consistently better than the others. Comparison of the absolute GWPs (after correction for the cup volume) also shows no consistent better or worse cup material. An evaluation of the methodological choices and the data sets used in the studies revealed their influence on the GWP. The differences in GWP can be attributed to a multitude of factors, i.e., cup material and weight, production processes, waste processes, allocation options, and data used. These factors basically represent different types of uncertainty. Sensitivity and scenario analyses provided only the influence of one factor at once. A systematic and simultaneous use of sensitivity and scenario analyses could, in a next research, result in more robust outcomes. -- Highlights: Conflicting results from life cycle assessment (LCA) on disposable cups GWP results of LCAs did not point to a best or worst cup material. Differences in GWP results are due to methodological choices and data sets used. Standardized LCA: transparency of LCA studies, but still different in approaches.

Harst, Eugenie van der, E-mail: eugenie.vanderharst@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Potting, Jos, E-mail: jose.potting@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands) [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Environmental Strategies Research (fms), KTH Royal Institute of Technology, SE-110 44 Stockholm (Sweden)

2013-11-15T23:59:59.000Z

91

Preparing sewage sludge for land application or surface disposal: A guide for preparers of sewage sludge on the monitoring, record keeping, and reporting requirements of the federal standards for the use of disposal of sewage sludge, 40 CFR part 503  

SciTech Connect (OSTI)

The document focuses on the monitoring, recordkeeping, and reporting requirements that apply to persons who prepare sewage sludge or a material derived from sewage sludge. It defines persons who prepare sewage sludge and then summarizes their general responsibilities. USEPA promulgated at 40 CFR Part 503 Phase 1 of the risk-based regulations that govern the final use or disposal of sewage sludge. The intent of the Federal program is to ensure that the use or disposal of sewage sludge occurs in a way that protects both human health and the environment. The Part 503 regulation establishes general requirements, pollutant limits, operational standards, and management practices, as well as monitoring, recordkeeping, and reporting requirements. These requirements apply to sewage sludge that is land applied, placed on a surface disposal site, or incinerated in a sewage sludge-only incinerator.

Not Available

1993-08-01T23:59:59.000Z

92

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

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

93

Salt caverns for oil field waste disposal.  

SciTech Connect (OSTI)

Salt caverns used for oil field waste disposal are created in salt formations by solution mining. When created, caverns are filled with brine. Wastes are introduced into the cavern by pumping them under low pressure. Each barrel of waste injected to the cavern displaces a barrel of brine to the surface. The brine is either used for drilling mud or is disposed of in an injection well. Figure 8 shows an injection pump used at disposal cavern facilities in west Texas. Several types of oil field waste may be pumped into caverns for disposal. These include drilling muds, drill cuttings, produced sands, tank bottoms, contaminated soil, and completion and stimulation wastes. Waste blending facilities are constructed at the site of cavern disposal to mix the waste into a brine solution prior to injection. Overall advantages of salt cavern disposal include a medium price range for disposal cost, large capacity and availability of salt caverns, limited surface land requirement, increased safety, and ease of establishment of individual state regulations.

Veil, J.; Ford, J.; Rawn-Schatzinger, V.; Environmental Assessment; RMC, Consultants, Inc.

2000-07-01T23:59:59.000Z

94

Large Component Removal/Disposal  

SciTech Connect (OSTI)

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

Wheeler, D. M.

2002-02-27T23:59:59.000Z

95

Processing Irradiated Beryllium For Disposal  

SciTech Connect (OSTI)

The purpose of this research was to develop a process for decontaminating irradiated beryllium that will allow it to be disposed of through normal radwaste channels. Thus, the primary objectives of this ongoing study are to remove the transuranic (TRU) isotopes to less than 100 nCi/g and remove {sup 60}Co, and {sup 137}Cs, to levels that will allow the beryllium to be contact handled. One possible approach that appears to have the most promise is aqueous dissolution and separation of the isotopes by selected solvent extraction followed by precipitation, resulting in a granular form for the beryllium that may be fixed to prevent it from becoming respirable and therefore hazardous. Beryllium metal was dissolved in nitric and fluorboric acids. Isotopes of {sup 241}Am, {sup 239}Pu, {sup 85}Sr, and {sup 137}Cs were then added to make a surrogate beryllium waste solution. A series of batch contacts was performed with the spiked simulant using chlorinated cobalt dicarbollide (CCD) and polyethylene glycol diluted with sulfone to extract the isotopes of Cs and Sr. Another series of batch contacts was performed using a combination of octyl (phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in tributyl phosphate (TBP) diluted with dodecane for extracting the isotopes of Pu and Am. The results indicate that greater than 99.9% removal can be achieved for each isotope with only three contact stages.

T. J. Tranter; R. D. Tillotson; N. R. Mann; G. R. Longhurst

2005-11-01T23:59:59.000Z

96

SciTech Connect: Deep Borehole Disposal Research: Geological...  

Office of Scientific and Technical Information (OSTI)

Deep Borehole Disposal Research: Geological Data Evaluation Alternative Waste Forms and Borehole Seals Citation Details In-Document Search Title: Deep Borehole Disposal Research:...

97

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

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

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...

98

A disposable, self-administered electrolyte test  

E-Print Network [OSTI]

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

Prince, Ryan, 1977-

2003-01-01T23:59:59.000Z

99

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect (OSTI)

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

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

2000-06-01T23:59:59.000Z

100

Economic assessment of CO? capture and disposal  

E-Print Network [OSTI]

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

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

Note: This page contains sample records for the topic "representing disposable personal" 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

Waste disposal options report. Volume 2  

SciTech Connect (OSTI)

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

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

1998-02-01T23:59:59.000Z

102

Personal Services Agreements Waivers  

E-Print Network [OSTI]

, State Controller's Office). All personal services contract activity will be reported through the state

103

Title I Disposal Sites Annual Report  

Broader source: Energy.gov [DOE]

This report presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements.

104

Pesticide fate in an aboveground disposal system  

E-Print Network [OSTI]

PESTICIDE FATE IN AN ABOVEGROUND DISPOSAL SYSTEM A Thesis by BRIAN RICHARD VANDERGLAS Submitted to the Graduate College of Texas A 8 M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 'l988... Major Subject: Soil Science PESTICIDE FATE IN AN ABOVEGROUND DISPOSAL SYSTEM A Thesis by BRIAN RICHARD VANDERGLAS Approved as to style and content by: K. W. Brown (Chair of Committee) John M. Sweeten (Member) Jack D. Price (Member) E. C. A...

Vanderglas, Brian Richard

2012-06-07T23:59:59.000Z

105

Solid waste disposal options: an optimum disposal model for the management of municipal solid waste  

E-Print Network [OSTI]

the Solid Waste Disposal Act and shifted the emphasis from disposal practices to recycling, resource recovery, and energy conversion of wastes. ' The Resource Conservation and Recovery Act of 1976 (RCRA) provided for the disposal of solid waste in such a... was constructed in 1930 in New York City. " But waste- to-energy technology development was hindered by poor reliability, poor efficiency, and low cost effectiveness. " The Resource Recovery Act of 1970 and RCRA of 1976, shifted the em- phasis in solid waste...

Haney, Brenda Ann

1989-01-01T23:59:59.000Z

106

Biohazardous Waste Disposal GuidelinesDescriptionStorage& LabelingTreatmentDisposal  

E-Print Network [OSTI]

Waste Sharps Waste Solid Lab Waste Liquid Waste Any of these devices if contaminated with biohazardousBiohazardous Waste Disposal GuidelinesDescriptionStorage& packaging LabelingTreatmentDisposal Mixed container. Container must be leakproof, ridgid, puncture resistant, clearly marked for biohazardous waste

Wikswo, John

107

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

SciTech Connect (OSTI)

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

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

108

General Engineer / Physical Scientist (Facility Representative)  

Broader source: Energy.gov [DOE]

Facility Representatives (FRs) are line management's on-site technical representative with responsibility for identifying and evaluating environmental, safety and health issues and concerns,...

109

Personal Data Vault: A Privacy Architecture for Mobile Personal Sensing  

E-Print Network [OSTI]

A The Detailed View of Personal Data Vault UCLA UCR Embedded Networked Sensing Personal Data Vault: a privacyRequired. Proposed Solution: Personal Data Vault, A Privacy

2009-01-01T23:59:59.000Z

110

PERSONAL DATA : / / (Attach Photo)  

E-Print Network [OSTI]

PERSONAL DATA : / / (Attach Photo) Passport / Please fill out in English Passport No Issued /TEL: /Mail : Spouse No Yes residing in Japan Not residing in Japan #12;PERSONAL DATA : / / Contact person & address in your country / Please fill out in English Name Relationship with you

Ejiri, Shinji

111

Electrochemical apparatus comprising modified disposable rectangular cuvette  

DOE Patents [OSTI]

Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

2013-09-10T23:59:59.000Z

112

Performance assessment methodology and preliminary results for low-level radioactive waste disposal in Taiwan.  

SciTech Connect (OSTI)

Sandia National Laboratories (SNL) and Taiwan's Institute for Nuclear Energy Research (INER) have teamed together to evaluate several candidate sites for Low-Level Radioactive Waste (LLW) disposal in Taiwan. Taiwan currently has three nuclear power plants, with another under construction. Taiwan also has a research reactor, as well as medical and industrial wastes to contend with. Eventually the reactors will be decomissioned. Operational and decommissioning wastes will need to be disposed in a licensed disposal facility starting in 2014. Taiwan has adopted regulations similar to the US Nuclear Regulatory Commission's (NRC's) low-level radioactive waste rules (10 CFR 61) to govern the disposal of LLW. Taiwan has proposed several potential sites for the final disposal of LLW that is now in temporary storage on Lanyu Island and on-site at operating nuclear power plants, and for waste generated in the future through 2045. The planned final disposal facility will have a capacity of approximately 966,000 55-gallon drums. Taiwan is in the process of evaluating the best candidate site to pursue for licensing. Among these proposed sites there are basically two disposal concepts: shallow land burial and cavern disposal. A representative potential site for shallow land burial is located on a small island in the Taiwan Strait with basalt bedrock and interbedded sedimentary rocks. An engineered cover system would be constructed to limit infiltration for shallow land burial. A representative potential site for cavern disposal is located along the southeastern coast of Taiwan in a tunnel system that would be about 500 to 800 m below the surface. Bedrock at this site consists of argillite and meta-sedimentary rocks. Performance assessment analyses will be performed to evaluate future performance of the facility and the potential dose/risk to exposed populations. Preliminary performance assessment analyses will be used in the site-selection process and to aid in design of the disposal system. Final performance assessment analyses will be used in the regulatory process of licensing a site. The SNL/INER team has developed a performance assessment methodology that is used to simulate processes associated with the potential release of radionuclides to evaluate these sites. The following software codes are utilized in the performance assessment methodology: GoldSim (to implement a probabilistic analysis that will explicitly address uncertainties); the NRC's Breach, Leach, and Transport - Multiple Species (BLT-MS) code (to simulate waste-container degradation, waste-form leaching, and transport through the host rock); the Finite Element Heat and Mass Transfer code (FEHM) (to simulate groundwater flow and estimate flow velocities); the Hydrologic Evaluation of Landfill performance Model (HELP) code (to evaluate infiltration through the disposal cover); the AMBER code (to evaluate human health exposures); and the NRC's Disposal Unit Source Term -- Multiple Species (DUST-MS) code (to screen applicable radionuclides). Preliminary results of the evaluations of the two disposal concept sites are presented.

Arnold, Bill Walter; Chang, Fu-lin (Institute of Nuclear Energy Research, Taiwan); Mattie, Patrick D.; Knowlton, Robert G.; Chuang, W-S (Institute of Nuclear Energy Research, Taiwan); Chi, L-M (Institute of Nuclear Energy Research, Taiwan); Jow, Hong-Nian; Tien, Norman C. (Institute of Nuclear Energy Research, Taiwan); Ho, Clifford Kuofei

2006-02-01T23:59:59.000Z

113

Guidance for writing permits for the use or disposal of sewage sludge. Draft report  

SciTech Connect (OSTI)

Section 405(d) of the Clean Water Act (CWA) directs the U.S. Environmental Protection Agency (EPA) to develop regulations containing guidelines for the use and disposal of sewage sludge. On February 19th, 1993, EPA published final regulations at 40 Code of Federal Regulations (CFR) Part 503 as the culmination of a major effort to develop technical standards in response to Section 405(d). These regulations govern three sewage sludge use and disposal practices: land application, surface disposal, and incineration. A key element in EPA's implementation of the Part 503 regulations is educating Agency and State personnel about these new requirements. Although the regulations are generally directly enforceable against all persons involved in the use and disposal of sewage sludge, they will also be implemented through permits issued to treatment works treating domestic sewage as defined in 40 CFR 122.22. Thus, the primary focus of the manual is to assist permit writers in incorporating the Part 503 requirements into permits; it serves as an update to the Guidance for Writing Case-by-Case Permit Conditions for Municipal Sewage Sludge (PB91-145508/HDM).

Not Available

1993-03-01T23:59:59.000Z

114

The disposal of orphan wastes using the greater confinement disposal concept  

SciTech Connect (OSTI)

In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ``home`` for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ``special-case`` or ``orphan`` wastes. This paper describes an ongoing project sponsored by the DOE`s Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes can be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs.

Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (USA); Dickman, P.T. [Department of Energy, Las Vegas, NV (USA). Nevada Operations Office

1991-02-01T23:59:59.000Z

115

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network [OSTI]

Demonstration LLNL Lawrence Livermore National Laboratory MSW Municipal Solid Waste OSHA Occupational Safety and Health Administration PPE Personal Protective Equipment POTW Publicly Owned Treatment Works RCRA Resource

116

Degradation Of Cementitious Materials Associated With Saltstone Disposal Units  

SciTech Connect (OSTI)

The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed saltstone. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative estimate (CE) and more defensible than the best estimate (BE). The combined effects of multiple phenomena are then considered to determine the most limiting degradation time scale for each cementitious material. Degradation times are estimated using a combination of analytic solutions from literature and numerical simulation codes provided through the DOE Cementitious Barriers Partnership (CBP) Software Toolbox (http://cementbarriers.org). For the SDU 2 design, the roof, wall, and floor components are projected to become fully degraded under Nominal conditions at 3866, 923, and 1413 years, respectively. For SDU 4 the roof and floor are estimated to be fully degraded under Nominal conditions after 1137 and 1407 years, respectively; the wall is assumed to be fully degraded at time zero in the most recent PA simulations. Degradation of these concrete barriers generally occurs from combined sulfate attack and corrosion of embedded steel following carbonation. Saltstone is projected to degrade very slowly by decalcification, with complete degradation occurring in excess of 200,000 years for any SDU type. Complete results are provided.

Flach, G. P; Smith, F. G. III

2013-03-19T23:59:59.000Z

117

Description and selection of soils at two oil shale disposal sites  

SciTech Connect (OSTI)

This paper presents geologic soil descriptions of two oil shale areas selected for soil sampling. Soil samples are to be collected specifically from areas designated for spent shale disposal. One shale disposal site is the Colorado Rio Blanco lease tract C-a, 84 Mesa. The other area is adjacent to the Clegg Creek Member of the New Albany shale in southeast Indiana. Site descriptions are considered to be fundamental before sampling in order to collect samples that are representative of the major parent material. The dominant parent materials found near Rio Blanco are basalt, sandstone, and marlstone. The dominant parent material in southeast Indiana is glacial till. The soils weathered from these materials have different physical and chemical characteristics. Collected samples will be representative of these characteristics. 6 refs., 3 figs.

McGowan, L.J.

1985-06-01T23:59:59.000Z

118

CSMRI Bagged Soil Disposal Summary Report  

E-Print Network [OSTI]

of radioactive/metals-contaminated soils and similar soils to a solid waste landfill in a letter dated August 26 Radioactive Materials License No. 1094-01. This document serves to provide a summary of the disposal as well. During the 2004 remediation work, approximately 1,870 cubic yards (cy) of radioactive

119

Chemical Container and Glassware Disposal Policy  

E-Print Network [OSTI]

Chemical Container and Glassware Disposal Policy If a barcoded bottle breaks, remove the barcode or take note of the number after safely cleaning up any chemical release. Provide the number to EH be obtained at Chemstores or Biostores. Grossly contaminated glassware (with chemical residue that can

Jia, Songtao

120

Economic disposal of solid oilfield wastes  

SciTech Connect (OSTI)

A variety of solid oilfield wastes, including produced sand, tank bottoms, and crude contaminated soils, are generated during drilling, production, and storage processes. Crude oil and crude-contaminated sands or soils are generally designated as nonhazardous wastes. However, these materials still must be disposed of in an environmentally acceptable manner. The problems can become most pressing as oil fields in urban areas reach the end of their productive lives and the productive lives and the properties are redeveloped for residential use. An economically and environmentally sound solution is to reinject the solid waste into sand formations through slurry fracture muds and cuttings in Alaska, the Gulf of Mexico, and the North Sea; naturally occurring radioactive materials in Alaska and the Gulf of Mexico; and large volumes of produced oily sand in the provinces of Alberta and Saskatchewan, Canada. The technique offers a number of economic and environmental advantages for disposal of solid oilfield wastes. When reinjecting into depleted oil sands, the crude waste is simply being returned to its place of origin. The long-term liability to the operator is eliminated, in marked contrast to surface storage or landfill disposal. Finally, fracture-injection costs are less than typical transport and landfill disposal costs for moderate to large quantities of solid waste

Bruno, M.S.; Qian, H.X.

1995-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Waste Handling and Disposal Biological Safety  

E-Print Network [OSTI]

plumbing services, EHS personnel wastewater treatment plant personnel, and the general public canWaste Handling and Disposal Biological Safety General Biosafety Practices (GBP) Why You Should Care on the next experiment. Are you working with r/sNA, biological toxins, human materials, needles, plasticware

Pawlowski, Wojtek

122

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS  

SciTech Connect (OSTI)

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

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

2007-06-21T23:59:59.000Z

123

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

Office of Environmental Management (EM)

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

124

Acceptance of Classified Excess Components for Disposal at Area 5  

SciTech Connect (OSTI)

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

Poling, Jeanne [National Security Technologies, LLC (United States); Saad, Max [Sandia National Lab., NM (United States)

2012-04-09T23:59:59.000Z

125

Statistically Equivalent Representative Volume Elements for Unidirectional  

E-Print Network [OSTI]

Statistically Equivalent Representative Volume Elements for Unidirectional Composite the statistically equivalent representative volume element (SERVE) are proposed for fiber-reinforced microstructures using a bilinear cohesive zone law. As introduced in the first article, a combination of statistical

Ghosh, Somnath

126

Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms  

SciTech Connect (OSTI)

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

Vinson, D.W.

1998-11-06T23:59:59.000Z

127

Landfill Disposal of CCA-Treated Wood with Construction and  

E-Print Network [OSTI]

Landfill Disposal of CCA-Treated Wood with Construction and Demolition (C&D) Debris: Arsenic phased out of many residential uses in the United States, the disposal of CCA-treated wood remains. Catastrophic events have also led to the concentrated disposal of CCA-treated wood, often in unlined landfills

Florida, University of

128

Cost of meeting geothermal liquid effluent disposal regulations  

SciTech Connect (OSTI)

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

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

1981-06-01T23:59:59.000Z

129

A Capital Market Test of Representativeness  

E-Print Network [OSTI]

A CAPITAL MARKET TEST OF REPRESENTATIVENESS A Dissertation by MOHAMMAD URFAN SAFDAR Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR... OF PHILOSOPHY May 2012 Major Subject: Accounting A Capital Market Test of Representativeness Copyright 2012 Mohammad Urfan Safdar A CAPITAL MARKET TEST OF REPRESENTATIVENESS A Dissertation...

Safdar, Mohammad

2012-07-16T23:59:59.000Z

130

Psykopater och psykotiska personer.  

E-Print Network [OSTI]

?? I Sverige begs ungefr vart tionde vldsbrott av personer i psykos och ca 40 procent av de brottslingar som r dmda fr grova vldsbrott (more)

Everstig, Cecilia

2007-01-01T23:59:59.000Z

131

Curriculum Vitae Personal Data  

E-Print Network [OSTI]

Curriculum Vitae 1 Personal Data Name : Dudy Darmawan Wijaya Place/Date of Birth : Bandung. Thesis: "Monitoring volcano deformation using GPS Method" #12;Curriculum Vitae 2 Working

Schuh, Harald

132

Technical and philosophical aspects of ocean disposal  

E-Print Network [OSTI]

Di sposai . Geological aspects Physical aspects Chemical aspects Biological aspects CHAPTER II. TECHNICAL ASPECTS OF OCEAN DISPOSAL Types of Waste Materials. Dredged materiais. Industrial wastes, DomestIc sewage wa tes Solid wastes Radloact..., can reduce the passage of light through the water column and cause damaging effects to the marine ecosystem. Each of five major oceans has pronounced gyral, or circular current motion (Fiaure 1. 1). The North Atlantic current system is comprised...

Zapatka, Marchi Charisse

1976-01-01T23:59:59.000Z

133

Persons under 18 may NOT: Drive a vehicle or forklift (except golf carts in certain circumstances)  

E-Print Network [OSTI]

, transport, or dispose of cooking oil or grease hotter than 100 degrees Fahrenheit · Work in freezers or meat.g., pool or billiard room, or bowling alley) · Work in barber shops · Work in construction, transportation for persons under age 18 For questions about wages or the child labor laws: Massachusetts Office

Fraden, Seth

134

Personal Services Agreements Waivers  

E-Print Network [OSTI]

Personal Services Agreements Waivers: Appendix A2 Responsible Administrative Units: Human Resources be performed by CSM staff. 4. Student Recruit Data Collection Services: Services include collecting a nation the adequate staff to perform these services. #12;Personal Services Agreements Waivers: Appendix A2 Responsible

135

Personal Services Agreements Waivers  

E-Print Network [OSTI]

Personal Services Agreements Waivers: Appendix A1 Responsible Administrative Units: Human Resources mapping, reviewing, surveying, and data collection for which CSM does not have staff qualified to perform these specialized services. #12;Personal Services Agreements Waivers: Appendix A1 Responsible Administrative Units

136

Web Personalization Magdalini Eirinaki  

E-Print Network [OSTI]

Web Mining for Web Personalization Magdalini Eirinaki Michalis Vazirgiannis Athens University of Economics and Business Department of Informatics #12;M.Eirinaki, M. Vazirgiannis Web Mining for Web Personalization 2PKDD 2005 Introduction Continuous growth in the size and the use of WWW Large and complicated web

Eirinaki, Magdalini

137

PSCloud: A Durable Context-Aware Personal Storage Cloud Sobir Bazarbayev, Matti Hiltunen, Kaustubh Joshi,  

E-Print Network [OSTI]

&T Labs Research Abstract Personal content from mobile devices is often irre- placeable, yet current's mo- bile devices, home servers, and cloud storage accounts to create a single unified personal of the user's devices. This represents a signifi- cant challenge given the increasing volume of a person

Fisher, Kathleen

138

Review of Yucca Mountain Disposal Criticality Studies  

SciTech Connect (OSTI)

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

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

2011-01-01T23:59:59.000Z

139

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energys mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2009-10-01T23:59:59.000Z

140

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energys mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energys mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-03-01T23:59:59.000Z

142

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energys mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-04-01T23:59:59.000Z

143

Personalized building comfort control  

E-Print Network [OSTI]

Creating an appropriate indoor climate is essential to worker productivity and personal happiness. It is also an area of large expenditure for building owners. And, with rising fuel costs, finding ways of reducing energy ...

Feldmeier, Mark Christopher, 1974-

2009-01-01T23:59:59.000Z

144

Headquarters Personal Property Management  

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

To establish procedures for managing Government personal property owned or leased by the Department of Energy and in the custody of DOE Headquarters employees, including those in the National Nuclear Security Administration. Cancels DOE HQ O 580.1A

2004-10-25T23:59:59.000Z

145

Crescent Junction Disposal Site Diversion Channel Design, North Side Disposal Cell Sources of Data:  

E-Print Network [OSTI]

Checked b"t me-Kao a MName A e4719 lProblem Statement: " Design erosion protection for the north slope of the disposal cell to prevent detrimental erosion from surface water flows from upland area, consistent with the requirements of 40 CFR Part 192 and NRC guidance in NUREG 1623.

unknown authors

146

Low-level radioactive mixed waste land disposal facility -- Permanent disposal  

SciTech Connect (OSTI)

Radioactive mixed waste (RMW) disposal at US Department of Energy (DOE) facilities is subject to the Resource Conservation and Recovery Act of 1976 (RCRA) and the Hazardous and Solid Waste Amendments of 1984 (HSWA). Westinghouse Hanford Company, in Richland, Washington, has completed the design of a radioactive mixed waste land disposal facility, which is based on the best available technology compliant with RCRA. When completed, this facility will provide permanent disposal of solid RMW, after treatment, in accordance with the Land Disposal Restrictions. The facility includes a double clay and geosynthetic liner with a leachate collection system to minimize potential leakage of radioactive or hazardous constituents from the landfill. The two clay liners will be capable of achieving a permeability of less than 1 {times} 10{sup {minus}7} cm/s. The two clay liners, along with the two high density polyethylene (HDPE) liners and the leachate collection and removal system, provide a more than conservative, physical containment of any potential radioactive and/or hazardous contamination.

Erpenbeck, E.G.; Jasen, W.G.

1993-03-01T23:59:59.000Z

147

Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)  

SciTech Connect (OSTI)

The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory constraints based on the intruder analysis are well above conservative estimates of the OSWDF inventory and, based on intruder disposal limits; about 7% of the disposal capacity is reached with the estimated OSWDF inventory.

Smith, Frank G.; Phifer, Mark A.

2014-01-22T23:59:59.000Z

148

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01T23:59:59.000Z

149

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31T23:59:59.000Z

150

Reactor Pressure Vessel Head Packaging & Disposal  

SciTech Connect (OSTI)

Reactor Pressure Vessel (RPV) Head replacements have come to the forefront due to erosion/corrosion and wastage problems resulting from the susceptibility of the RPV Head alloy steel material to water/boric acid corrosion from reactor coolant leakage through the various RPV Head penetrations. A case in point is the recent Davis-Besse RPV Head project, where detailed inspections in early 2002 revealed significant wastage of head material adjacent to one of the Control Rod Drive Mechanism (CRDM) nozzles. In lieu of making ASME weld repairs to the damaged head, Davis-Besse made the decision to replace the RPV Head. The decision was made on the basis that the required weld repair would be too extensive and almost impractical. This paper presents the packaging, transport, and disposal considerations for the damaged Davis-Besse RPV Head. It addresses the requirements necessary to meet Davis Besse needs, as well as the regulatory criteria, for shipping and burial of the head. It focuses on the radiological characterization, shipping/disposal package design, site preparation and packaging, and the transportation and emergency response plans that were developed for the Davis-Besse RPV Head project.

Wheeler, D. M.; Posivak, E.; Freitag, A.; Geddes, B.

2003-02-26T23:59:59.000Z

151

Municipal solid waste disposal in Portugal  

SciTech Connect (OSTI)

In recent years municipal solid waste (MSW) disposal has been one of the most important environmental problems for all of the Portuguese regions. The basic principles of MSW management in Portugal are: (1) prevention or reduction, (2) reuse, (3) recovery (e.g., recycling, incineration with heat recovery), and (4) polluter-pay principle. A brief history of legislative trends in waste management is provided herein as background for current waste management and recycling activities. The paper also presents and discusses the municipal solid waste management in Portugal and is based primarily on a national inquiry carried out in 2003 and directed to the MSW management entities. Additionally, the MSW responsibility and management structure in Portugal is presented, together with the present situation of production, collection, recycling, treatment and elimination of MSW. Results showed that 96% of MSW was collected mixed (4% was separately collected) and that 68% was disposed of in landfill, 21% was incinerated at waste-to-energy plants, 8% was treated at organic waste recovery plants and 3% was delivered to sorting. The average generation rate of MSW was 1.32 kg/capita/day.

Magrinho, Alexandre [Mechanical Engineering Department, Escola Superior de Tecnologia de Setubal, Campus IPS, Estefanilha, Setubal (Portugal); Didelet, Filipe [Mechanical Engineering Department, Escola Superior de Tecnologia de Setubal, Campus IPS, Estefanilha, Setubal (Portugal); Semiao, Viriato [Mechanical Engineering Department, Instituto Superior Tecnico, Av. Rovisco Pais, 1049-001 Lisbon (Portugal)]. E-mail: ViriatoSemiao@ist.utl.pt

2006-07-01T23:59:59.000Z

152

Remedial Action and Waste Disposal Conduct of OperationsMatrix  

SciTech Connect (OSTI)

This Conduct of Operations (CONOPS) matrix incorporates the Environmental Restoration Disposal Facility (ERDF) CONOPS matrix (BHI-00746, Rev. 0). The ERDF CONOPS matrix has been expanded to cover all aspects of the RAWD project. All remedial action and waste disposal (RAWD) operations, including waste remediation, transportation, and disposal at the ERDF consist of construction-type activities as opposed to nuclear power plant-like operations. In keeping with this distinction, the graded approach has been applied to the developmentof this matrix.

M. A. Casbon.

1999-05-24T23:59:59.000Z

153

FY 2006 ANNUAL REVIEW-SALTSTONE DISPOSAL FACILITY PERFORMANCE ASSESSMENT  

SciTech Connect (OSTI)

The Z-Area Saltstone Disposal Facility (SDF) consists of two disposal units, Vaults 1 and 4, described in the Performance Assessment (PA) (WSRC 1992). The FY06 PA Annual Review concludes that both vaults contain much lower levels of radionuclides (curies) than that allowed by the PA. The PA controls established to govern waste operations and monitor disposal facility performance are determined to be adequate.

Crapse, K; Benjamin Culbertson, B

2007-03-15T23:59:59.000Z

154

Fees For Disposal Of Hazardous Waste Or Substances (Alabama)  

Broader source: Energy.gov [DOE]

The article lists annual payments to be made to counties, restrictions on disposal of hazardous waste, additional fees collected by counties and penalties.

155

Evaluation of Options for Permanent Geologic Disposal of Spent...  

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

policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring...

156

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect (OSTI)

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

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

2000-02-01T23:59:59.000Z

157

Low-Level Waste Disposal Alternatives Analysis Report  

SciTech Connect (OSTI)

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

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

2006-09-01T23:59:59.000Z

158

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

Broader source: Energy.gov [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...

159

Used Fuel Disposition Campaign Disposal Research and Development...  

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

generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has...

160

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

Broader source: Energy.gov [DOE]

This legislation authorizes the state's entrance into the Southwestern Low-Level Radioactive Waste Disposal Compact, which provides for the cooperative management of low-level radioactive waste....

Note: This page contains sample records for the topic "representing disposable personal" 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

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

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

162

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

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

163

Repository Reference Disposal Concepts and Thermal Load Management...  

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

Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clayshale, salt, crystalline,...

164

ash disposal site: Topics by E-print Network  

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

OF PRINCE GEORGE: SNOW DISPOSAL AT THE LANSDOWNE ROAD WASTEWATER TREATMENT CENTRE DOE FRAP WASTEWATER TREATMENT CENTRE ACKNOWLEDGEMENTS Funding for this study was provided...

165

ash disposal sites: Topics by E-print Network  

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

OF PRINCE GEORGE: SNOW DISPOSAL AT THE LANSDOWNE ROAD WASTEWATER TREATMENT CENTRE DOE FRAP WASTEWATER TREATMENT CENTRE ACKNOWLEDGEMENTS Funding for this study was provided...

166

Disposable Carbon Nanotube Modified Screen-Printed Biosensor...  

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

Carbon Nanotube Modified Screen-Printed Biosensor for Amperometric Detection of Organophosphorus Pesticides and Nerve Disposable Carbon Nanotube Modified Screen-Printed Biosensor...

167

An Introduction to Venture Capital Granite representatives  

E-Print Network [OSTI]

May 2006 An Introduction to Venture Capital #12;2 Granite representatives Sam Kingsland ­ Managing;3 Introduction to Granite Ventures Founded in 1992 Granite has 9 investment professionals Over $1B under

Anderson, Richard

168

General Engineer/Physical Scientist (Facility Representative)  

Broader source: Energy.gov [DOE]

A successful candidate in this position will serve as an on-site technical representative to identify and evaluate environmental, safety, and health issues and concerns; as well as diagnose root...

169

CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY  

SciTech Connect (OSTI)

During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

Cozzi, A.; Duncan, A.

2010-01-28T23:59:59.000Z

170

Sludge utilization and disposal in Virginia  

SciTech Connect (OSTI)

This state-of-the-art study was initiated to determine the problem issues, present knowledge about the issues, and additional research needs in the area of land disposal of municipal sewage sludge. Three questionnaires were developed to survey technically oriented professional, county extension agents, and Virginia NPDES permit holders to obtain these groups' views on problems and deficiencies needing further investigation. Another phase of the study was to conduct an extensive review of the literature on the subject of land application of sewage sludge. Listings of pertinent literature relating to land application with specific interest toward potentially toxic metals, pathogens, nitrogen, and phosphorus were obtained and reviewed. Additional research is needed in the following areas: a method that accurately estimates metal availability within the soil; a method to determine the potential for a disease outbreak from controlled application of treated municipal sewage sludge; a more precise method of N-balancing; the impact of P loading on water quality.

Martens, D.C.; McCart, G.D.; Reneau, R.B. Jr; Simpson, T.W.; Ban-Kiat, T.

1982-10-01T23:59:59.000Z

171

Disposable sludge dewatering container and method  

DOE Patents [OSTI]

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

Cole, Clifford M. (1905 Cottonwood Dr., Aiken, SC 29803)

1993-01-01T23:59:59.000Z

172

Radioactive waste disposal in thick unsaturated zones  

SciTech Connect (OSTI)

Portions of the Great Basin are undergoing crustal extension and have unsaturated zones as much as 600 meters thick. These areas contain multiple natural barriers capable of isolating solidified toxic wastes from the biosphere for tens of thousands to perhaps hundreds of thousands of years. An example of the potential utilization of such arid zone environments for toxic waste isolation is the burial of transuranic radioactive wastes at relatively shallow depths (15 to 100 meters) in Sedan Crater, Yucca Flat, Nevada. The volume of this man-made crater is several times that of the projected volume of such wastes to the year 2000. Disposal in Sedan Crater could be accomplished at a savings on the order of $0.5 billion, in comparison with current schemes for burial of such wastes in mined repositories at depths of 600 to 900 meters, and with an apparently equal likelihood of waste isolation from the biosphere. 4 figures.

Winograd, I.J.

1981-06-26T23:59:59.000Z

173

Mixed waste characterization, treatment & disposal focus area  

SciTech Connect (OSTI)

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

NONE

1996-08-01T23:59:59.000Z

174

A Change in Envirocare's Disposal Cell Design  

SciTech Connect (OSTI)

Envirocare of Utah, Inc. operates a Low Level Radioactive Waste (LLRW) and 11e. disposal facility in the Utah west dessert. Envirocare disposes of LLRW in above ground cells. A seven-foot excavation lined with two feet of clay comprises the cell floor. Approximately 22 feet of waste is then placed in the cell in one-foot thick compacted lifts. The cover system consists of a nine-foot clay radon barrier and three-foot rock erosion barrier. This is required to prevent radon emissions at the surface of the radon barrier from exceeding 20 pCi/m2s, the radon release standard in Criterion 6 of 10 CFR 40. The required thickness of the current clay radon barrier cover was based on the original radon flux model used to evaluate the safety of Envirocare's proposed LLRW and 11e.(2) license operations. Because of the lack of actual measurements, universally conservative values were used for the long-term moisture content and the radon diffusion coefficients of the waste and radon barrier material. Since receiving its license, Envirocare has collected a number of samples from the radon barrier and waste material to determine their actual radon attenuation characteristics, including the long-term moisture content and the associated radon diffusion coefficient. In addition, radon flux measurements have been performed to compare the model calculations with the calculated results. The results from these analyses indicate that the initial modeling input parameters, specifically the long-term moisture content and the radon diffusion coefficient, are more conservative than that needed to ensure compliance with the applicable regulatory requirements.

Rogers, T.

2002-02-25T23:59:59.000Z

175

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network [OSTI]

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

176

1 INSTRODUCTION In the concept of geological radioactive waste disposal,  

E-Print Network [OSTI]

1 INSTRODUCTION In the concept of geological radioactive waste disposal, argillite is being of the radioactive waste disposal, the host rock will be subjected to various thermo-hydro-mechanical loadings, thermal solicitation comes from the heat emitting from the radioactive waste packages. On one hand

Boyer, Edmond

177

User Guide for Disposal of Unwanted Items and Electronic Waste  

E-Print Network [OSTI]

is the Recycle department at 502-6808 o For more information on the UCSF Sustainability program visit: http://sustainability.ucsf.edu/stay_informed/recycling_resources consulting support Ensuring proper reuse, recycle, or disposal Maintaining regulatory and policy compliance metal and wood o Waste/trash management o Recycle, reuse or disposal of materials D&S does not process o

Mullins, Dyche

178

A model approach to radioactive waste disposal at Sellafield  

E-Print Network [OSTI]

A model approach to radioactive waste disposal at Sellafield R. 5. Haszeldine* and C. Mc of the great environmentalproblems of our age is the safe disposal of radioactive waste for geological time of the BorrowdaleVolcanic Group (BVG).Nirex plan to site their nuclear waste Repository at 650 m below sea- level

Haszeldine, Stuart

179

Composite analysis E-area vaults and saltstone disposal facilities  

SciTech Connect (OSTI)

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

Cook, J.R.

1997-09-01T23:59:59.000Z

180

Introducing Fraunhofer Personal reflection  

E-Print Network [OSTI]

­ they are not part of the University. The Centres form an integral part of that country's innovation system while for Sustainable Energy Systems. The Fraunhofer model is certainly applicable to the UK (the Fraunhofer modelIntroducing Fraunhofer Personal reflection I have taken a keen interest in Fraunhofer Geselleschaft

Mottram, Nigel

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


181

Curriculum Vitae PERSONAL INFORMATION  

E-Print Network [OSTI]

Curriculum Vitae 1 PERSONAL INFORMATION Name: Tomomi Shimogori Title: Ph.D. Affiliation : RIKEN BSI, 824-9. #12;Curriculum Vitae 2 2. Igarashi K, Koga K, He Y, Shimogori T, Ekimoto H, Kashiwagi K. 274, 1942-8. #12;Curriculum Vitae 3 10. Iwata S, Sato Y, Asada M, Takagi M, Tsujimoto A, Inaba T

Kazama, Hokto

182

CURRICULUM VITAE PERSONAL INFORMATION  

E-Print Network [OSTI]

CURRICULUM VITAE PERSONAL INFORMATION Name RYABOV, Boris Address Ropazu 5 - 13, Riga, LV-1039 telescope RATAN-600. Page 1 ­ Curriculum vitae of RYABOV, Boris #12;· Dates 1984 ­ 1987, 1977 ­ 1979, 1974 good · Writing skills basic · Verbal skills excellent Page 2 ­ Curriculum vitae of RYABOV, Boris #12

Ryabov, Boris I.

183

Curriculum Vitae Personal information  

E-Print Network [OSTI]

Europass Curriculum Vitae Personal information First name(s) / Surname(s) Fedor / Marchenko Address 1/3 - Curriculum vitae of Marchenko Fedor #12;Education and training Dates Title of qualification Page 2/3 - Curriculum vitae of Marchenko Fedor #12;Other skills and competences Driving licence present

184

An iconic approach to representing climate change  

E-Print Network [OSTI]

1 An iconic approach to representing climate change Saffron Jessica O'Neill A thesis submitted-experts to be meaningfully engaged with the issue of climate change. This thesis investigates the value of engaging non-experts with climate change at the individual level. Research demonstrates that individuals perceive climate change

Feigon, Brooke

185

FOOD SECURITY FUEL INDEPENDENCE These projects represent  

E-Print Network [OSTI]

FOOD SECURITY FUEL INDEPENDENCE These projects represent a huge effort to determine and improve pressing challenges. ASH 1% ASH 1% ASH 1% OTHERS 6% OTHERS 6% OTHERS 6% OIL 2% OIL 10% OIL 20% SUCROSE 45% LIPID CANE Produce and store oil in the stem in place of sugar During photosynthesis, sugarcane

Bashir, Rashid

186

PROCEDURES FOR DISPOSING OF WASTE CHEMICALS 1. All containers submitted for disposal must be clearly labeled with the following information  

E-Print Network [OSTI]

-duty plastic bags. Tape all containers of chemically-contaminated dry materials securely shut and label. Container Is - Indicate P (plastic), G (glass), or M (metal). Physical State - Indicate if the material8/99 PROCEDURES FOR DISPOSING OF WASTE CHEMICALS 1. All containers submitted for disposal must

187

International program to study subseabed disposal of high-level radioactive wastes  

SciTech Connect (OSTI)

This report provides an overview of the international program to study seabed disposal of nuclear wastes. Its purpose is to inform legislators, other policy makers, and the general public as to the history of the program, technological requirements necessary for feasibility assessment, legal questions involved, international coordination of research, national policies, and research and development activities. Each of these major aspects of the program is presented in a separate section. The objective of seabed burial, similar to its continental counterparts, is to contain and to isolate the wastes. The subseabed option should not be confuesed with past practices of ocean dumping which have introduced wastes into ocean waters. Seabed disposal refers to the emplacement of solidified high-level radioactive waste (with or without reprocessing) in certain geologically stable sediments of the deep ocean floor. Specially designed surface ships would transport waste canisters from a port facility to the disposal site. Canisters would be buried from a few tens to a few hundreds of meters below the surface of ocean bottom sediments, and hence would not be in contact with the overlying ocean water. The concept is a multi-barrier approach for disposal. Barriers, including waste form, canister, ad deep ocean sediments, will separate wastes from the ocean environment. High-level wastes (HLW) would be stabilized by conversion into a leach-resistant solid form such as glass. This solid would be placed inside a metallic canister or other type of package which represents a second barrier. The deep ocean sediments, a third barrier, are discussed in the Feasibility Assessment section. The waste form and canister would provide a barrier for several hundred years, and the sediments would be relied upon as a barrier for thousands of years. 62 references, 3 figures, 2 tables.

Carlin, E.M.; Hinga, K.R.; Knauss, J.A.

1984-01-01T23:59:59.000Z

188

Generic Argillite/Shale Disposal Reference Case  

SciTech Connect (OSTI)

Radioactive waste disposal in a deep subsurface repository hosted in clay/shale/argillite is a subject of widespread interest given the desirable isolation properties, geochemically reduced conditions, and widespread geologic occurrence of this rock type (Hansen 2010; Bianchi et al. 2013). Bianchi et al. (2013) provides a description of diffusion in a clay-hosted repository based on single-phase flow and full saturation using parametric data from documented studies in Europe (e.g., ANDRA 2005). The predominance of diffusive transport and sorption phenomena in this clay media are key attributes to impede radionuclide mobility making clay rock formations target sites for disposal of high-level radioactive waste. The reports by Hansen et al. (2010) and those from numerous studies in clay-hosted underground research laboratories (URLs) in Belgium, France and Switzerland outline the extensive scientific knowledge obtained to assess long-term clay/shale/argillite repository isolation performance of nuclear waste. In the past several years under the UFDC, various kinds of models have been developed for argillite repository to demonstrate the model capability, understand the spatial and temporal alteration of the repository, and evaluate different scenarios. These models include the coupled Thermal-Hydrological-Mechanical (THM) and Thermal-Hydrological-Mechanical-Chemical (THMC) models (e.g. Liu et al. 2013; Rutqvist et al. 2014a, Zheng et al. 2014a) that focus on THMC processes in the Engineered Barrier System (EBS) bentonite and argillite host hock, the large scale hydrogeologic model (Bianchi et al. 2014) that investigates the hydraulic connection between an emplacement drift and surrounding hydrogeological units, and Disposal Systems Evaluation Framework (DSEF) models (Greenberg et al. 2013) that evaluate thermal evolution in the host rock approximated as a thermal conduction process to facilitate the analysis of design options. However, the assumptions and the properties (parameters) used in these models are different, which not only make inter-model comparisons difficult, but also compromise the applicability of the lessons learned from one model to another model. The establishment of a reference case would therefore be helpful to set up a baseline for model development. A generic salt repository reference case was developed in Freeze et al. (2013) and the generic argillite repository reference case is presented in this report. The definition of a reference case requires the characterization of the waste inventory, waste form, waste package, repository layout, EBS backfill, host rock, and biosphere. This report mainly documents the processes in EBS bentonite and host rock that are potentially important for performance assessment and properties that are needed to describe these processes, with brief description other components such as waste inventory, waste form, waste package, repository layout, aquifer, and biosphere. A thorough description of the generic argillite repository reference case will be given in Jov Colon et al. (2014).

Zheng, Liange; Jov& #233; Colon, Carlos; Bianchi, Marco; Birkholzer, Jens

2014-08-08T23:59:59.000Z

189

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

2012-07-01T23:59:59.000Z

190

Data structures and apparatuses for representing knowledge  

DOE Patents [OSTI]

Data structures and apparatuses to represent knowledge are disclosed. The processes can comprise labeling elements in a knowledge signature according to concepts in an ontology and populating the elements with confidence values. The data structures can comprise knowledge signatures stored on computer-readable media. The knowledge signatures comprise a matrix structure having elements labeled according to concepts in an ontology, wherein the value of the element represents a confidence that the concept is present in an information space. The apparatus can comprise a knowledge representation unit having at least one ontology stored on a computer-readable medium, at least one data-receiving device, and a processor configured to generate knowledge signatures by comparing datasets obtained by the data-receiving devices to the ontologies.

Hohimer, Ryan E; Thomson, Judi R; Harvey, William J; Paulson, Patrick R; Whiting, Mark A; Tratz, Stephen C; Chappell, Alan R; Butner, Robert S

2014-02-18T23:59:59.000Z

191

Yucca Mountain Climate Technical Support Representative  

SciTech Connect (OSTI)

The primary objective of Project Activity ORD-FY04-012, Yucca Mountain Climate Technical Support Representative, was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding.

Sharpe, Saxon E

2007-10-23T23:59:59.000Z

192

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

Broader source: Energy.gov [DOE]

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

193

Systems engineering programs for geologic nuclear waste disposal  

SciTech Connect (OSTI)

The design sequence and system programs presented begin with general approximate solutions that permit inexpensive analysis of a multitude of possible wastes, disposal media, and disposal process properties and configurations. It then continues through progressively more precise solutions as parts of the design become fixed, and ends with repository and waste form optimization studies. The programs cover both solid and gaseous waste forms. The analytical development, a program listing, a users guide, and examples are presented for each program. Sensitivity studies showing the effects of disposal media and waste form thermophysical properties and repository layouts are presented as examples.

Klett, R. D.; Hertel, Jr., E. S.; Ellis, M. A.

1980-06-01T23:59:59.000Z

194

Immobilized low-level waste disposal options configuration study  

SciTech Connect (OSTI)

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

Mitchell, D.E.

1995-02-01T23:59:59.000Z

195

Demilitarization and disposal technologies for conventional munitions and energetic materials  

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

196

Minor actinide waste disposal in deep geological boreholes  

E-Print Network [OSTI]

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

Sizer, Calvin Gregory

2006-01-01T23:59:59.000Z

197

Used Nuclear Fuels Storage, Transportation, and Disposal Analysis...  

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

Used Nuclear Fuels Storage, Transportation, and Disposal Analysis Resource and Data System (UNF-ST&DARDS) Apr 08 2014 10:00 AM - 11:00 AM John M. Scaglione, ORNL staff, Oak Ridge...

198

A microelectronic design for low-cost disposable chemical sensors  

E-Print Network [OSTI]

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

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

2004-01-01T23:59:59.000Z

199

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

Broader source: Energy.gov [DOE]

This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental...

200

Canister design for deep borehole disposal of nuclear waste  

E-Print Network [OSTI]

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

Hoag, Christopher Ian

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study  

SciTech Connect (OSTI)

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

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

2012-09-18T23:59:59.000Z

202

Low-Level Radioactive Waste Disposal Act (Pennsylvania)  

Broader source: Energy.gov [DOE]

This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and...

203

Waste Disposal Site and Radioactive Waste Management (Iowa)  

Broader source: Energy.gov [DOE]

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

204

Radionuclide limits for vault disposal at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site is developing a facility called the E-Area Vaults which will serve as the new radioactive waste disposal facility beginning early in 1992. The facility will employ engineered below-grade concrete vaults for disposal and above-grade storage for certain long-lived mobile radionuclides. This report documents the determination of interim upper limits for radionuclide inventories and concentrations which should be allowed in the disposal structures. The work presented here will aid in the development of both waste acceptance criteria and operating limits for the E-Area Vaults. Disposal limits for forty isotopes which comprise the SRS waste streams were determined. The limits are based on total facility and vault inventories for those radionuclides which impact groundwater, and or waste package concentrations for those radionuclides which could affect intruders.

Cook, J.R.

1992-02-04T23:59:59.000Z

205

Land disposal of water treatment plant sludge -- A feasibility analysis  

SciTech Connect (OSTI)

In this study, the following alternative disposal methods for the Buffalo Pound Water Treatment Sludge were evaluated: landfilling, discharge into sanitary sewers, long-term lagooning, use in manufacturing, co-composting, alum recovery and land application. Land application was chosen at the best disposal alternative. Preliminary design resulted in a 1% dry alum sludge loading rate (25 tonnes/ha), requiring 35 ha over a nine-year period and a phosphorus fertilizer supplement of about 50kg/ha.

Viraraghavan, T.; Multon, L.M.; Wasylenchuk, E.J.

1998-07-01T23:59:59.000Z

206

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

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

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

2011-01-01T23:59:59.000Z

207

Geological Disposal Concept Selection Aligned with a Voluntarism Process - 13538  

SciTech Connect (OSTI)

The UK's Radioactive Waste Management Directorate (RWMD) is currently at a generic stage in its implementation programme. The UK site selection process is a voluntarist process and, as yet, no communities have decided to participate. RWMD has set out a process to describe how a geological disposal concept would be selected for the range of higher activity wastes in the UK inventory, including major steps and decision making points, aligned with the stages of the UK site selection process. A platform of information is being developed on geological disposal concepts at various stages of implementation internationally and, in order to build on international experience, RWMD is developing its approach to technology transfer. The UK has a range of different types of higher activity wastes with different characteristics; therefore a range of geological disposal concepts may be needed. In addition to identifying key aspects for considering the compatibility of different engineered barrier systems for different types of waste, RWMD is developing a methodology to determine minimum separation distances between disposal modules in a co-located geological disposal facility. RWMD's approach to geological disposal concept selection is intended to be flexible, recognising the long term nature of the project. RWMD is also committed to keeping alternative radioactive waste management options under review; an approach has been developed and periodic reviews of alternative options will be published. (authors)

Crockett, Glenda; King, Samantha [Nuclear Decommissioning Authority, Building 587, Curie Avenue, Harwell Oxford, Didcot, Oxfordshire, OX11 0RH (United Kingdom)] [Nuclear Decommissioning Authority, Building 587, Curie Avenue, Harwell Oxford, Didcot, Oxfordshire, OX11 0RH (United Kingdom)

2013-07-01T23:59:59.000Z

208

University of Delaware Laboratory Chemical Waste Disposal Guide ALL CHEMICAL WASTE MUST BE DISPOSED OF THROUGH THE  

E-Print Network [OSTI]

experiments and procedures Non-Returnable gas cylinders Batteries Spent solvents, Stains, Strippers, Thinners, Fertilizers Formaldehyde and Formalin Solutions Mercury containing items (other heavy metals) Liquid OR SMALL CONTAINERS IMPORTANT: DO NOT DISPOSE OF REACTIVE, AIR SENSITIVE, OR OXIDIZER SAMPLES

Firestone, Jeremy

209

Personality and group interaction  

E-Print Network [OSTI]

that "prize Chips will be awarded equally to each person in the group based on the total number of blocks still standing in the tower at the end of the 15 seconds". b) In the contrient condition, subjects were told that "Prize Chips will be awarded only... to the individual with the most blocks still standing in the tower at the end of the 15 seconds. If there are any ties in terms of the number blocks on the tower and there is no clear winner, then no prize chips will be distributed". 6. Only one tower may...

Hair, Elizabeth Catherine

1996-01-01T23:59:59.000Z

210

Personal continuous air monitor  

DOE Patents [OSTI]

A personal continuous air monitor capable of giving immediate warning of the presence of radioactivity has a filter/detector head to be worn in the breathing zone of a user, containing a filter mounted adjacent to radiation detectors, and a preamplifier. The filter/detector head is connected to a belt pack to be worn at the waist or on the back of a user. The belt pack contains a signal processor, batteries, a multichannel analyzer, a logic circuit, and an alarm. An air pump also is provided in the belt pack for pulling air through the filter/detector head by way of an air tube.

Morgan, Ronald G. (Los Alamos, NM); Salazar, Samuel A. (Albuquerque, NM)

2000-01-01T23:59:59.000Z

211

Representing the vacuum polarization on de Sitter  

SciTech Connect (OSTI)

Previous studies of the vacuum polarization on de Sitter have demonstrated that there is a simple, noncovariant representation of it in which the physics is transparent. There is also a cumbersome, covariant representation in which the physics is obscure. Despite being unwieldy, the latter form has a powerful appeal for those who are concerned about de Sitter invariance. We show that nothing is lost by employing the simple, noncovariant representation because there is a closed form procedure for converting its structure functions to those of the covariant representation. We also present a vastly improved technique for reading off the noncovariant structure functions from the primitive diagrams. And we discuss the issue of representing the vacuum polarization for a general metric background.

Leonard, Katie E.; Woodard, Richard P. [Department of Physics, University of Florida, Gainesville, Florida 32611 (United States)] [Department of Physics, University of Florida, Gainesville, Florida 32611 (United States); Prokopec, Tomislav [Institute of Theoretical Physics (ITP) and Spinoza Institute, Utrecht University, Postbus 80195, 3508 TD Utrecht (Netherlands)] [Institute of Theoretical Physics (ITP) and Spinoza Institute, Utrecht University, Postbus 80195, 3508 TD Utrecht (Netherlands)

2013-03-15T23:59:59.000Z

212

PIA - Human Resources - Personal Information Change Request ...  

Office of Environmental Management (EM)

PIA - Human Resources - Personal Information Change Request - Idaho National Engineering Laboratory PIA - Human Resources - Personal Information Change Request - Idaho National...

213

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

SciTech Connect (OSTI)

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

Royce, B.A.

1985-09-01T23:59:59.000Z

214

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

SciTech Connect (OSTI)

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

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

2012-11-15T23:59:59.000Z

215

Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods  

SciTech Connect (OSTI)

According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

Veil, J.A.

1997-09-01T23:59:59.000Z

216

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

SciTech Connect (OSTI)

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

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

1997-10-01T23:59:59.000Z

217

Remediation of a Former USAF Radioactive Material Disposal Site  

SciTech Connect (OSTI)

This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of the United States Air Force. Included is a discussion of methods and strategies that were used to successfully exhume and characterize the wastes for proper disposal at offsite disposal facilities. Worker and environmental protection measures are also described. Information gained from this project may be used at other similar project sites. A total of nine burial tubes had been identified for excavation, characterization, and removal from the site. The disposal tubes were constructed of 4-ft lengths of concrete pipe buried upright with the upper ends flush with ground surface. Initial ground level observations of the burial tubes indicated that some weathering had occurred; however, the condition of the subsurface portions of the tubes was unknown. Soil excavation occurred in 1-foot lifts in order that the tubes could be inspected and to allow for characterization of the soils at each stage of the excavation. Due to the weight of the concrete pipe and the condition of the piping joints it was determined that special measures would be required to maintain the tubes intact during their removal. Special tube anchoring and handling methods were required to relocate the tubes from their initial positions to a staging area where they could be further characterized. Characterization of the disposal tubes was accomplished using a combination of gamma spectroscopy and activity mapping methods. Important aspects of the project included the use of specialized excavation and disposal tube reinforcement measures to maintain the disposal tubes intact during excavation, removal and subsequent characterization. The non-intrusive gamma spectroscopy and data logging methods allowed for effective characterization of the wastes while minimizing disposal costs. In addition, worker exposures were maintained ALARA as a result of the removal and characterization methods employed.

Hoffman, D. E.; Cushman, M; Tupyi, B.; Lambert, J.

2003-02-25T23:59:59.000Z

218

UW-Approved Waste Disposal, Recycling and Treatment Sites Hazardous waste disposal at the University of Washington is coordinated by the EH&S Environmental Programs Office  

E-Print Network [OSTI]

UW-Approved Waste Disposal, Recycling and Treatment Sites Hazardous waste disposal, WA Rabanco Recycling Co Landfill Roosevelt, WA Waste Management, Columbia Ridge Landfill Arlington Refrigeration Shop Recovery Seattle, WA Fluorescent light tubes - intact Ecolights NW Recycle Seattle, WA Shop

Wilcock, William

219

Thermal-mechanical modeling of deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

Disposal of high-level radioactive waste, including spent nuclear fuel, in deep (3 to 5 km) boreholes is a potential option for safely isolating these wastes from the surface and near-surface environment. Existing drilling technology permits reliable and cost-effective construction of such deep boreholes. Conditions favorable for deep borehole disposal in crystalline basement rocks, including low permeability, high salinity, and geochemically reducing conditions, exist at depth in many locations, particularly in geologically stable continental regions. Isolation of waste depends, in part, on the effectiveness of borehole seals and potential alteration of permeability in the disturbed host rock surrounding the borehole. Coupled thermal-mechanical-hydrologic processes induced by heat from the radioactive waste may impact the disturbed zone near the borehole and borehole wall stability. Numerical simulations of the coupled thermal-mechanical response in the host rock surrounding the borehole were conducted with three software codes or combinations of software codes. Software codes used in the simulations were FEHM, JAS3D, Aria, and Adagio. Simulations were conducted for disposal of spent nuclear fuel assemblies and for the higher heat output of vitrified waste from the reprocessing of fuel. Simulations were also conducted for both isotropic and anisotropic ambient horizontal stress in the host rock. Physical, thermal, and mechanical properties representative of granite host rock at a depth of 4 km were used in the models. Simulation results indicate peak temperature increases at the borehole wall of about 30 C and 180 C for disposal of fuel assemblies and vitrified waste, respectively. Peak temperatures near the borehole occur within about 10 years and decline rapidly within a few hundred years and with distance. The host rock near the borehole is placed under additional compression. Peak mechanical stress is increased by about 15 MPa (above the assumed ambient isotropic stress of 100 MPa) at the borehole wall for the disposal of fuel assemblies and by about 90 MPa for vitrified waste. Simulated peak volumetric strain at the borehole wall is about 420 and 2600 microstrain for the disposal of fuel assemblies and vitrified waste, respectively. Stress and volumetric strain decline rapidly with distance from the borehole and with time. Simulated peak stress at and parallel to the borehole wall for the disposal of vitrified waste with anisotropic ambient horizontal stress is about 440 MPa, which likely exceeds the compressive strength of granite if unconfined by fluid pressure within the borehole. The relatively small simulated displacements and volumetric strain near the borehole suggest that software codes using a nondeforming grid provide an adequate approximation of mechanical deformation in the coupled thermal-mechanical model. Additional modeling is planned to incorporate the effects of hydrologic processes coupled to thermal transport and mechanical deformation in the host rock near the heated borehole.

Arnold, Bill Walter; Hadgu, Teklu

2010-12-01T23:59:59.000Z

220

Oilfield surveillance using personal computers  

SciTech Connect (OSTI)

Personal computers and hand-held calculators were used in the development of an oilfield surveillance and data gathering system. Producing wells, steam injection wells, water plants, steam generators, and well workovers are all monitored through the use of personal computers. Personal computers provide an accurate and timely method of verifying and editing data as well as providing immediate retrieval of information vital to the daily operation of a thermal recovery oilfield.

Moore, J.B.

1985-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Using Process Knowledge to Manage Disposal Classification of Ion-Exchange Resin - 13566  

SciTech Connect (OSTI)

It has been previously shown by EPRI [1] that Class B and C resins represent a small portion by volume of the overall generation of radioactively contaminated resins. In fact, if all of the resins were taken together the overall classification would meet Class A disposal requirements. Lowering the classification of the ion exchange resins as they are presented for disposal provides a path for minimizing the amount of waste stored. Currently there are commercial options for blending wastes from various generators for Class A disposal in development. The NRC may have by this time introduced changes and clarifications to the Branch Technical Position (BTP) on Concentration Averaging and Encapsulation [2] that may ultimately add more flexibility to what can be done at the plant level. The BTP has always maintained that mixtures of resins that are combined for ALARA purposes or operational efficiency can be classified on the basis of the mixture. This is a point often misinterpreted and misapplied. This paper will address options that can be exercised by the generator that can limit B and C waste generation by more rigorous tracking of generation and taking advantage of the normal mix of wastes. This can be achieved through the monitoring of reactor coolant chemistry data and coupled with our knowledge of radionuclide production mechanisms. This knowledge can be used to determine the overall accumulation of activity in ion-exchange resins and provides a 'real-time' waste classification determination of the resin and thereby provide a mechanism to reduce the production of waste that exceeds class A limits. It should be noted that this alternative approach, although rarely used in a nuclear power plant setting, is acknowledged in the original BTP on classification [3] as a viable option for determining radionuclide inventories for classification of waste. Also included is a discussion of an examination performed at the Byron plant to estimate radionuclide content in the final waste stream from upstream sampling of reactor coolant and fuel pool water. (authors)

Bohnsack, Jonathan N.; James, David W. [DW James Consulting, LLC 855 Village Center Drive No. 330 North Oaks, MN 55127 (United States)] [DW James Consulting, LLC 855 Village Center Drive No. 330 North Oaks, MN 55127 (United States)

2013-07-01T23:59:59.000Z

222

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

SciTech Connect (OSTI)

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

NONE

2000-10-12T23:59:59.000Z

223

Scholarship Search Profile Personal Information  

E-Print Network [OSTI]

Scholarship Search Profile Personal Information Name: ____________________________________ Address) ________________________________________________________________________ ________________________________________________________________________ ________________________________________________________________________ Work Experience: List most recent job first Employer/Company Name _______________________________________________________________ Reference: Name and telephone _____________________________________________ Employer/Company Name

Mather, Patrick T.

224

Government Personal Property Asset Management  

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

Establishes procedures for managing Government personal property owned or leased by and in the custody of Department of Energy (DOE) Headquarters employees. Cancels HQ 1400.1.

1998-05-11T23:59:59.000Z

225

Integrated Disposal Facility FY2011 Glass Testing Summary Report  

SciTech Connect (OSTI)

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

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

2011-09-29T23:59:59.000Z

226

Unique method of ash disposal can benefit marine life  

SciTech Connect (OSTI)

As more communities turn to waste-to-energy facilities to help solve their solid waste disposal problems, the amount of ash created by these facilities increases. Incineration of solid waste produces particulate residues which are often rich in lead, cadmium, copper, and zinc because of the concentration which occurs as a result of reduction. It has been shown that such metals can sometimes be leached from ash residues, giving rise to special concerns that incineration ashes be disposed of in an environmentally acceptable manner. In urban coastal areas where landfills are few and increasingly distant, ocean disposal of stabilized incineration residues (SIR) may provide an acceptable alternative to current landfill practices. In May 1985, a research program was initiated at the Marine Sciences Research Center to examine the feasibility of utilizing SIR for artificial reef construction in the ocean. Results of these studies showed that particulate incineration residues could be combined with cement to form a solid block possessing physical properties necessary for ocean disposal. The stabilized residues were subjected to regulatory extraction protocols, and in no instance did the metal concentrations in the leachates exceed the regulatory limits for toxicity. Bioassays revealed no adverse effects on the phytoplankton communities exposed to elutriate concentrations higher than could be encountered under normal disposal conditions. The success of the laboratory studies resulted in securing the necessary permits for the placement of an artificial habitat constructed using SIR in coastal wasters. Results from this program are described.

Roethel, F.J.; Breslin, V.T. (State Univ. of New York, Stony Brook (USA))

1988-10-01T23:59:59.000Z

227

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

SciTech Connect (OSTI)

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

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

1986-06-01T23:59:59.000Z

228

DOE SNF technology development necessary for final disposal  

SciTech Connect (OSTI)

Existing technology is inadequate to allow safe disposal of the entire inventory of US Department of Energy (DOE) spent nuclear fuel (SNF). Needs for SNF technology development were identified for each individual fuel type in the diverse inventory of SNF generated by past, current, and future DOE materials production, as well as SNF returned from domestic and foreign research reactors. This inventory consists of 259 fuel types with different matrices, cladding materials, meat composition, actinide content, and burnup. Management options for disposal of SNF include direct repository disposal, possible including some physical or chemical preparation, or processing to produce a qualified waste form by using existing aqueous processes or new treatment processes. Technology development needed for direct disposal includes drying, mitigating radionuclide release, canning, stabilization, and characterization technologies. While existing aqueous processing technology is fairly mature, technology development may be needed to apply one of these processes to SNF different than for which the process was originally developed. New processes to treat SNF not suitable for disposal in its current form were identified. These processes have several advantages over existing aqueous processes.

Hale, D.L.; Fillmore, D.L.; Windes, W.E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1996-02-01T23:59:59.000Z

229

MIE -H&S -08 -Personal Protection Personal Protection  

E-Print Network [OSTI]

type of work. Safety glasses 2. Safety boots are optional, except when heavy parts are to be moved or worked on. Open toe shoes must not worn at the work site or in the laboratories. Safety boots 3. GlovesMIE - H&S - 08 - Personal Protection Personal Protection 1. Safety glasses must be worn when any

230

3Q CY2005 (PDF), Facility Representative Program Performance...  

Office of Environmental Management (EM)

3Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report 3Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report...

231

DOE Honors WIPP Representative for Cutting Travel Costs, Greenhouse...  

Energy Savers [EERE]

DOE Honors WIPP Representative for Cutting Travel Costs, Greenhouse Gas Emissions DOE Honors WIPP Representative for Cutting Travel Costs, Greenhouse Gas Emissions June 29, 2012 -...

232

Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal  

SciTech Connect (OSTI)

On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m{sup 2} of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite.

Not Available

1993-12-31T23:59:59.000Z

233

Earth melter and method of disposing of feed materials  

DOE Patents [OSTI]

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

Chapman, C.C.

1994-10-11T23:59:59.000Z

234

Classified Component Disposal at the Nevada National Security Site  

SciTech Connect (OSTI)

The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012.

Poling, J. [NSTec; Arnold, P. [NSTec; Saad, M. [SNL; DiSanza, F.; Cabble, K. [NNSA/NSO

2012-11-05T23:59:59.000Z

235

Earth melter and method of disposing of feed materials  

SciTech Connect (OSTI)

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

Chapman, Christopher C. (Richland, WA)

1994-01-01T23:59:59.000Z

236

Crystalline ceramics: Waste forms for the disposal of weapons plutonium  

SciTech Connect (OSTI)

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

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

1995-05-01T23:59:59.000Z

237

Subproject L-045H 300 Area Treated Effluent Disposal Facility  

SciTech Connect (OSTI)

The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The 300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations.

Not Available

1991-06-01T23:59:59.000Z

238

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria  

SciTech Connect (OSTI)

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

W. Mahlon Heileson

2006-10-01T23:59:59.000Z

239

Designing the Personal Data Stream: Enabling Participatory Privacy in Mobile Personal Sensing  

E-Print Network [OSTI]

Awareness Forum. (2009). Personal Data Guardianship Code.form of distributed personal data collection (Eagle, 2008;to collect and respond to personal data about their habits,

2009-01-01T23:59:59.000Z

240

Representative Atmospheric Plume Development for Elevated Releases  

SciTech Connect (OSTI)

An atmospheric explosion of a low-yield nuclear device will produce a large number of radioactive isotopes, some of which can be measured with airborne detection systems. However, properly equipped aircraft may not arrive in the region where an explosion occurred for a number of hours after the event. Atmospheric conditions will have caused the radioactive plume to move and diffuse before the aircraft arrives. The science behind predicting atmospheric plume movement has advanced enough that the location of the maximum concentrations in the plume can be determined reasonably accurately in real time, or near real time. Given the assumption that an aircraft can follow a plume, this study addresses the amount of atmospheric dilution expected to occur in a representative plume as a function of time past the release event. The approach models atmospheric transport of hypothetical releases from a single location for every day in a year using the publically available HYSPLIT code. The effective dilution factors for the point of maximum concentration in an elevated plume based on a release of a non-decaying, non-depositing tracer can vary by orders of magnitude depending on the day of the release, even for the same number of hours after the release event. However, the median of the dilution factors based on releases for 365 consecutive days at one site follows a power law relationship in time, as shown in Figure S-1. The relationship is good enough to provide a general rule of thumb for estimating typical future dilution factors in a plume starting at the same point. However, the coefficients of the power law function may vary for different release point locations. Radioactive decay causes the effective dilution factors to decrease more quickly with the time past the release event than the dilution factors based on a non-decaying tracer. An analytical expression for the dilution factors of isotopes with different half-lives can be developed given the power law expression for the non-decaying tracer. If the power-law equation for the median dilution factor, Df, based on a non-decaying tracer has the general form Df=a?t?^(-b) for time t after the release event, then the equation has the form Df=e^(-?t)at^(-b) for a radioactive isotope, where ? is the decay constant for the isotope.

Eslinger, Paul W.; Lowrey, Justin D.; McIntyre, Justin I.; Miley, Harry S.; Prichard, Andrew W.

2014-03-03T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Politics and promises of nuclear waste disposal: the view from Nevada  

SciTech Connect (OSTI)

DOE`s betrayal of the principles and standards of the Nuclear Waste Policy Act (NWPA) has distorted the agency`s repository-siting decisions. Leadership is needed to make midcourse corrections and to return to the promise of state-federal cooperation on which the act was built. NWPA managed to incorporate the interests of diverse factions into a decision-making process that was viewed as an equitable and workable solution to the nation`s nuclear waste disposal dilemma. The House of Representatives subcommittees report documents conclusively a substantial and pervasive bias in favor of the selection of sites at Yucca Mountain and Hanford and a politization of the siting process.

Bryan, R.H.

1987-10-01T23:59:59.000Z

242

Packet personal radiation monitor  

DOE Patents [OSTI]

A personal radiation monitor of the chirper type is provided for detecting ionizing radiation. A battery powered high voltage power supply is used to generate and apply a high voltage bias to a G-M tube radiation sensor. The high voltage is monitored by a low-loss sensing network which generates a feedback signal to control the high voltage power supply such that the high voltage bias is recharged to +500 VDC when the current pulses of the sensor, generated by the detection of ionizing radiatonevents, discharges the high voltage bias to +450 VDC. During the high voltage recharge period an audio transducer is activated to produce an audible ''chirp''. The rate of the ''chirps'' is controlled by the rate at which the high voltage bias is recharged, which is proportional to the radiation field intensity to which the sensor is exposed. The chirp rate sensitivity is set to be approximately 1.5 (chirps/min/MR/hr.). The G-M tube sensor is used in a current sensing mode so that the device does not paralyze in a high radiation field. 2 figs.

Phelps, J.E.

1988-03-31T23:59:59.000Z

243

Packet personal radiation monitor  

DOE Patents [OSTI]

A personal radiation monitor of the chirper type is provided for detecting ionizing radiation. A battery powered high voltage power supply is used to generate and apply a high voltage bias to a G-M tube radiation sensor. The high voltage is monitored by a low-loss sensing network which generates a feedback signal to control the high voltage power supply such that the high voltage bias is recharged to +500 VDC when the current pulses of the sensor, generated by the detection of ionizing radiation events, discharges the high voltage bias to +450 VDC. During the high voltage recharge period an audio transducer is activated to produce an audible "chirp". The rate of the "chirps" is controlled by the rate at which the high voltage bias is recharged, which is proportional to the radiation field intensity to which the sensor is exposed. The chirp rate sensitivity is set to be approximately 1.5 (chirps/min/MR/hr.). The G-M tube sensor is used in a current sensing mode so that the device does not paralyze in a high radiation field.

Phelps, James E. (Knoxville, TN)

1989-01-01T23:59:59.000Z

244

DIVISION OF RECREATIONAL SPORTS Personal Training  

E-Print Network [OSTI]

Information Personal Training Policies Waiver Client Data Questionnaire Health Status Questionnaire PersonalDIVISION OF RECREATIONAL SPORTS Personal Training New Client Packet Personal Training Package to Purdue Rec Sports Personal Training Getting Started The information included in this packet is everything

Pittendrigh, Barry

245

Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2010-10-01T23:59:59.000Z

246

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14  

SciTech Connect (OSTI)

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Schneider, K.J.

1982-09-01T23:59:59.000Z

247

Possible effects of UO/sub 2/ oxidation on light water reactor spent fuel performance in long-term geologic disposal  

SciTech Connect (OSTI)

Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO/sub 2/) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO/sub 2/ oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented.

Almassy, M.Y.; Woodley, R.E.

1982-08-01T23:59:59.000Z

248

Advance disposal fees and recycling: Partners or foes?  

SciTech Connect (OSTI)

A political trend of shifting government responsibilities from the federal to the state and local level is beginning to take hold in many municipalities this year. Evidence of this shift recently was codified by the passage of Congress`s unfunded mandates bills, which require a panel review of any federal government mandates that create a cost burden of at least $50 million on state and local government. Expecting to be freed from the yoke of the most costly unfunded federal laws, many states are taking a second look at their expensive recycling laws and considering reassessment of how funding mechanisms are structured. This search for ways to raise revenue has renewed the continuing debate over advance disposal fees (ADFs), which are included in the cost of a product to pay for its ultimate disposal or reuse. These ADFs have been used for several years in a majority of US states to help handle scrap tire disposal. Due to concern over fire hazards posed by the nation`s growing scrap tire piles, several states have implemented a $1--$2 fee on each tire to help pay for disposal, most of which have been reasonably successful.

Woods, R.

1995-05-01T23:59:59.000Z

249

Doctoral Defense "Biogeochemical evaluation of disposal options for arsenic-  

E-Print Network [OSTI]

of arsenic. Arsenic contamination is particularly severe in Bangladesh and India, where access to landfills from groundwater in West Bengal, India. Under a range of leaching tests, determinants of arsenic fate in non-landfill disposal conditions and provide additional insight on arsenic

Kamat, Vineet R.

250

Disposal of CCA-treated Wood: An Evaluation of  

E-Print Network [OSTI]

Disposal of CCA-treated Wood: An Evaluation of Existing and Alternative Management Options (FINAL CHARACTERISTICS OF CCA-TREATED WOOD ASH II.1 Sample Preparation 10 II.2 Laboratory Methods 15 II.3 Laboratory Results 24 CHAPTER III, SORTING TECHNOLOGIES FOR SEPARATING TREATED WOOD FROM UNTREATED WOOD III.1

Florida, University of

251

Support of the Iraq nuclear facility dismantlement and disposal program  

SciTech Connect (OSTI)

Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

Coates, Roger [International Atomic Energy Agency - IAEA, Wagramer Strasse 5, P.O. Box 100 - 1400 Vienna (Austria); Cochran, John; Danneels, Jeff [Sandia National Laboratories (United States); Chesser, Ronald; Phillips, Carlton; Rogers, Brenda [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX 79409 (United States)

2007-07-01T23:59:59.000Z

252

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

SciTech Connect (OSTI)

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

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

1994-12-12T23:59:59.000Z

253

Business and Finance Surplus Materials Disposal Policy # 4.51  

E-Print Network [OSTI]

and guidelines. B. Surplus property is defined as "equipment, furniture and other materials/supplies" no longer. Chemical recycling, second use of chemicals, and the disposal of unusable chemicals, radioactive are the responsibility of Transportation and Parking Services, 160 Bevis Hall, 1080 Carmack Road, 292-9341. B. Computer

254

On-Farm Storage and Disposal of Sorghum Grain.  

E-Print Network [OSTI]

APRIL 1963 ON-FARM - STORAGE AND DISPOSAL OF SORGHUM GRAIN -- THE AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS TEXAS AGRICULTURAL EXPERIMENT STATION R. E. PATTERSON. DIRECTOR. COLLEGE ST+TION, TEXAS IN COOPERATION WITH THE U. S. DEPARTMENT... OF AGRICULTURE summary The sorghum storage space. Utilization increases resulted from an increased awareness and acceptance by feeders and millers...

Brown, Charles W.; Moore, Clarence A.

1963-01-01T23:59:59.000Z

255

Preliminary Transportation, Aging and Disposal Canister System Performance Specification  

SciTech Connect (OSTI)

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

C.A Kouts

2006-11-22T23:59:59.000Z

256

Integrated Disposal Facility FY 2012 Glass Testing Summary Report  

SciTech Connect (OSTI)

PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

2013-03-29T23:59:59.000Z

257

Laboratory to demolish excavation enclosures at Material Disposal Area B  

E-Print Network [OSTI]

to hazardous and radiological contamination while excavating and packaging contaminated debris and soil from of a highly successful environmental cleanup project at Material Disposal Area B," said Ed Worth, federal project manager #12;- 2 - with the National Nuclear Security Administration's Los Alamos Site Office. "We

258

Hydrological Evaluation of Septic Disposal Field Design in Sloping Terrains  

E-Print Network [OSTI]

. Steenhuis7 Abstract: The most common form of onsite domestic wastewater treatment in the United States; Slopes; Wastewater treatment; Waste disposal. Introduction The most common form of onsite wastewater treatment is the septic system Wastewater 1991 . Over 50 million people in the United States use septic

Walter, M.Todd

259

Long-Term Performance of Uranium Tailings Disposal Cells - 13340  

SciTech Connect (OSTI)

Recently, there has been interest in the performance and evolution of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell covers because some sites are not compliant with groundwater standards. Field observations of UMTRA disposal cells indicate that rock covers tend to become vegetated and that saturated conductivities in the upper portion of radon barriers may increase due to freeze/thaw cycles and biointrusion. This paper describes the results of modeling that addresses whether these potential changes and transient drainage of moisture in the tailings affect overall performance of the disposal cells. A numerical unsaturated/saturated 3-dimensional flow model was used to simulate whether increases in saturated conductivities in radon barriers with rock covers affect the overall performance of the disposal cells using field data from the Shiprock, NM, UMTRA site. A unique modeling approach allowed simulation with daily climatic conditions to determine changes in moisture and moisture flux from the disposal cell. Modeling results indicated that increases in the saturated conductivity at the top of radon barrier do not influence flux from the tailings with time because the tailings behave similar hydraulically to the radon barrier. The presence of a thin layer of low conductivity material anywhere in the cover or tailings restricts flux in the worst case to the saturated conductivity of that material. Where materials are unsaturated at depth within the radon barrier of tailings slimes, conductivities are typically less than 10{sup -8} centimeters per second. If the low conductivity layer is deep within the disposal cell, its saturated properties are less likely to change with time. The significance of this modeling is that operation and maintenance of the disposal cells can be minimized if they are allowed to progress to a natural condition with some vegetation and soil genesis. Because the covers and underlying tailings have a very low saturated hydraulic conductivity after transient drainage, eventually the amount of moisture leaving the tailings has a negligible effect on groundwater quality. Although some of the UMTRA sites are not in compliance with the groundwater standards, the explanation may be legacy contamination from mining, or earlier higher fluxes from the tailings or unlined processing ponds. Investigation of other legacy sources at the UMTRA sites may help explain persistent groundwater contamination. (authors)

Bostick, Kent; Daniel, Anamary; Pill, Ken [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States)] [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States); Tachiev, Georgio; Noosai, Nantaporn; Villamizar, Viviana [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)] [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)

2013-07-01T23:59:59.000Z

260

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

SciTech Connect (OSTI)

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

Cook, J

2005-05-26T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Update on cavern disposal of NORM-contaminated oil field wastes.  

SciTech Connect (OSTI)

Some types of oil and gas production and processing wastes contain naturally occurring radioactive material (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. Argonne National Laboratory has previously evaluated the feasibility, legality, risk and economics of disposing of nonhazardous oil field wastes, other than NORM waste, in salt caverns. Cavern disposal of nonhazardous oil field waste, other than NORM waste, is occurring at four Texas facilities, in several Canadian facilities, and reportedly in Europe. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns as well. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, a review of federal regulations and regulations from several states indicated that there are no outright prohibitions against NORM disposal in salt caverns or other Class II wells, except for Louisiana which prohibits disposal of radioactive wastes or other radioactive materials in salt domes. Currently, however, only Texas and New Mexico are working on disposal cavern regulations, and no states have issued permits to allow cavern disposal of NORM waste. On the basis of the costs currently charged for cavern disposal of nonhazardous oil field waste (NOW), NORM waste disposal in caverns is likely to be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

Veil, J. A.

1998-09-22T23:59:59.000Z

262

GT Human Resources PERSONAL DATA FORM  

E-Print Network [OSTI]

GT Human Resources PERSONAL DATA FORM Page 1 Updated: 05/01/2014 Student Employee? Yes No Print clearly using black or blue ink. Personal Information Name) __________________________________________________________________________________________ (City) (State) (Zip) (County) Personal Telephone #: (_______)________-__________ GT Work Telephone

Jacobs, Laurence J.

263

GT Human Resources PERSONAL DATA FORM  

E-Print Network [OSTI]

GT Human Resources PERSONAL DATA FORM Page 1 Updated: 0//201 Student Employee? Yes No Print clearly.: _________________________________ Job Title: Email: _________________________________ #12;GT Human Resources PERSONAL DATA FORM Page 2 using black or blue ink. Personal Information Name

Garmestani, Hamid

264

GT Human Resources PERSONAL DATA FORM  

E-Print Network [OSTI]

GT Human Resources PERSONAL DATA FORM Page 1 Updated: 05/01/2014 Student Employee? Yes No Print.: _________________________________ Job Title: _________________________________ #12;GT Human Resources PERSONAL DATA FORM Page 2 Updated clearly using black or blue ink. Personal Information Name

Jacobs, Laurence J.

265

UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1  

SciTech Connect (OSTI)

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

NONE

1995-10-01T23:59:59.000Z

266

An Online Tool for Personal Data Collection and Exploration  

E-Print Network [OSTI]

2 Personal Data and156 B.1 Personal Data Applications . . . . . . . . . . . .de- signed for personal data and the everyday and discuss

Yau, Nathan Chun-Yin

2013-01-01T23:59:59.000Z

267

Chemistry of Personalized Solar Energy  

E-Print Network [OSTI]

Personalized energy (PE) is a transformative idea that provides a new modality for the planets energy future. By providing solar energy to the individual, an energy supply becomes secure and available to people of both ...

Nocera, Daniel G.

268

Stephen Bruce Vardeman Personal Data  

E-Print Network [OSTI]

1 5/13 Stephen Bruce Vardeman Personal Data Citizenship: U.S.A. Security Clearance: L (Department Institute of Mathematical Statistics (Life Member) Offices Held in Professional Societies Program Chair, ASA

Vardeman, Stephen B.

269

Sustainable Building Tax Credit (Personal)  

Broader source: Energy.gov [DOE]

SB 463, enacted in April 2007, established a personal tax credit and a corporate tax credit for sustainable buildings in New Mexico. The tax credits apply to both commercial and residential...

270

Device-transparent personal storage  

E-Print Network [OSTI]

Users increasingly store data collections such as digital photographs on multiple personal devices, each of which typically presents the user with a storage management interface isolated from the contents of all other ...

Strauss, Jacob A. (Jacob Alo), 1979-

2010-01-01T23:59:59.000Z

271

DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN,  

E-Print Network [OSTI]

i DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN, CHAOPRAYA Sludge (FS) management and lacking of data on FS collection, treatment and disposal. Nevertheless, FS

Richner, Heinz

272

Concept study: Use of grout vaults for disposal of long-length contaminated equipment  

SciTech Connect (OSTI)

Study considers the potential for use of grout vaults for disposal of untreated long length equipment removed from waste tanks. Looks at ways to access vaults, material handling, regulatory aspects, and advantages and disadvantages of vault disposal.

Clem, D.K.

1994-09-21T23:59:59.000Z

273

Assessment of Disposal Options for DOE-Managed High-Level Radioactive...  

Office of Environmental Management (EM)

Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and...

274

Basis for Identification of Disposal Options for R and D for...  

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

Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel...

275

Affordable avatar control system for personal robots  

E-Print Network [OSTI]

Social robots (personal robots) emphasize individualized social interaction and communication with people. To maximize communication capacity of a personal robot, designers make it more anthropomorphic (or zoomorphic), and ...

Lee, Jun Ki, S. M. Massachusetts Institute of Technology

2009-01-01T23:59:59.000Z

276

Personal Property Policy | Department of Energy  

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

of Energy Acquisition Regulations (DEAR) DOE Order 580.1A, Department of Energy Personal Property Management Program DOE Guide 580.1-1, Personal Property Management Guide...

277

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect (OSTI)

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

278

Environmental regulations and technology: use and disposal of municipal waste-water sludge  

SciTech Connect (OSTI)

The document describes the five major sludge use/disposal options currently available--land application, distribution and marketing of sludge products, land-filling, incineration, and ocean disposal--and factors influencing their selection and implementation. It also provides an initial framework for evaluating sludge use/disposal alternatives, and describes accepted and proven use/disposal technologies and Federal regulations pertinent to sludge management.

Not Available

1984-09-01T23:59:59.000Z

279

Interface control document between PUREX Plant Transition and Solid Waste Disposal Division  

SciTech Connect (OSTI)

The interfacing responsibilities regarding solid waste management are described for the Solid Waste Disposal Division and the PUREX Transition Organization.

Carlson, A.B.

1995-09-01T23:59:59.000Z

280

Taxes In, Garbage Out The Need for Better Solid Waste Disposal  

E-Print Network [OSTI]

.................................................................................................................... 8 THE FISCAL AND ENVIRONMENTAL IMPACTS OF CURRENT DISPOSAL PRACTICES.....................9 Fiscal..................................................................................... 2 History of the Municipal System Impact

Note: This page contains sample records for the topic "representing disposable personal" 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

Generation, Use, Disposal, and Management Options for CCA-Treated Wood  

E-Print Network [OSTI]

Generation, Use, Disposal, and Management Options for CCA-Treated Wood May 1998 Helena Solo, INVENTORY OF CCA-TREATED WOOD IN FLORIDA II.1 Characteristics of the Florida Wood Treatment Industry in 1996 10 II.2 Generation and Disposal of Cca-treated Wood 14 II.3 Disposal Reservoirs for Cca-treated Wood

Florida, University of

282

LOCAL ARRANGEMENTS FOR WASTE DISPOSAL (MAIN SITE) Landfill (England & Wales) Regulations 2002  

E-Print Network [OSTI]

the Chemicals Technicians when they have empty glass bottles for disposal. EMPTY PLASTIC CHEMICAL BOTTLES Plastic containers that have open necks, e.g. solvent bottles, may be washed out and disposed of via be disposed of as non-hazardous waste. EMPTY (GLASS) CHEMICAL BOTTLES University regulations governing

Paxton, Anthony T.

283

Impacts of Shale Gas Wastewater Disposal on Water Quality in Western Pennsylvania  

E-Print Network [OSTI]

Impacts of Shale Gas Wastewater Disposal on Water Quality in Western Pennsylvania Nathaniel R. In Pennsylvania, oil and gas wastewater is sometimes treated at brine treatment facilities and discharged to local bioaccumulation in localized areas of shale gas wastewater disposal. INTRODUCTION The safe disposal of large

Jackson, Robert B.

284

Environmental Impact of Wastewater Disposal in the Florida Keys, Monroe County Tom Higginbotham  

E-Print Network [OSTI]

Environmental Impact of Wastewater Disposal in the Florida Keys, Monroe County Tom Higginbotham University of Florida Soil and Water Science #12;Environmental Impact of Wastewater Disposal in the Florida affecting the normally oligotrophic marine waters. Typical methods of wastewater disposal include large

Ma, Lena

285

The WIPP is the nation's first geologic facility designed for permanent disposal of transuranic  

E-Print Network [OSTI]

, New Mexico to dispose of this waste. The TRU waste being disposed at the WIPP is packaged into drums-level waste and spent nuclear fuel. The WIPP has a total capacity of 6.2 million cubic feet of TRU waste." Disposal of TRU mixed waste at the WIPP requires EPA and state approval. (EPA regulates the radioactive

286

Visualizing Scalar Fields Represented by Adaptive Square Triangulations  

E-Print Network [OSTI]

[Sabella 88], ab­ sorption and reflection [Max 95] providing a means of representing the field by a colored

287

Great Lakes Electrical Sales Company Job Posting Title: Sales Representative  

E-Print Network [OSTI]

personal and business goals of expanding customer base in the marketing area. Works within the sales individuals should send a cover letter and resume to shawn.offenbacher@glesco.net #12;

Heller, Barbara

288

Abstract--Navigation for blind persons represents a challenge for researchers in vision substitution. In this field, one of the  

E-Print Network [OSTI]

. TDU and similar devices are principally used in researches about psycho-motricity, but they are often

Payan, Yohan

289

Integrated process for coalbed brine and methane disposal  

SciTech Connect (OSTI)

This paper describes a technology and project to demonstrate and commercialize a brine disposal process for converting the brine stream of a coalbed gas producing site into clean water for agricultural use and dry solids that can be recycled for industrial consumption. The process also utilizes coalbed methane (CBM) released from coal mining for the combustion process thereby substantially reducing the potential for methane emissions to the atmosphere. The technology is ideally suited for the treatment and disposal of produced brines generated from the development of coal mines and coalbed methane resources worldwide. Over the next 10 to 15 years, market potential for brine elimination equipment and services is estimated to be in the range of $1 billion.

Byam, J.W. Jr.; Tait, J.H.; Brandt, H.

1996-12-31T23:59:59.000Z

290

Regulatory requirements affecting disposal of asbestos-containing waste  

SciTech Connect (OSTI)

Many U.S. Department of Energy (DOE) facilities are undergoing decontamination and decommissioning (D&D) activities. The performance of these activities may generate asbestos-containing waste because asbestos was formerly used in many building materials, including floor tile, sealants, plastics, cement pipe, cement sheets, insulating boards, and insulating cements. The regulatory requirements governing the disposal of these wastes depend on: (1) the percentage of asbestos in the waste and whether the waste is friable (easily crumbled or pulverized); (2) other physical and chemical characteristics of the waste; and (3) the State in which the waste is generated. This Information Brief provides an overview of the environment regulatory requirements affecting disposal of asbestos-containing waste. It does not address regulatory requirements applicable to worker protection promulgated under the Occupational Safety and Health Act (OSHAct), the Mining Safety and Health Act (MSHA), or the Toxic Substances Control Act (TSCA).

NONE

1995-11-01T23:59:59.000Z

291

Relevance of biotic pathways to the long-term regulation of nuclear waste disposal: Phase 2, Final report  

SciTech Connect (OSTI)

The results reported here establish the relevance and propose a method for including biotic transport in the assessment and licensing process for commercial low-level waste disposal sites. Earlier work identified the biotic transport mechanisms and process scenarios linking biotic transport with dose to man, and developed models for assessment of impacts. Model modification and improvement efforts in enhancing the ability to represent soil erosion and soil transport within the trench cover. Two alternative hypotheses on plant root uptake were incorporated into the model to represent transport of radionuclides by roots that penetrate the buried waste. Enhancements were also made to the scenario for future site intruder activities. Representation of waste package decomposition in the model was confirmed as the best available alternative. Results from sensitivity analyses indicate that additional information is needed to evaluate the alternative hypotheses for plant root uptake of buried wastes. Site-specific evaluations of the contribution from biotic transport to the potential dose to man establish the relevance in the assessment process. The BIOPORT/MAXI1 computer software package is proposed for dose assessments of commercial low-level waste disposal sites.

McKenzie, D.H.; Cadwell, L.L.; Kennedy, W.E. Jr.; Prohammer, L.A.; Simmons, M.A.

1986-11-01T23:59:59.000Z

292

The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan  

SciTech Connect (OSTI)

The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational disposal facility or disapproval to initiate construction of a new facility.''

DEFFENBAUGH, M.L.

2000-08-01T23:59:59.000Z

293

Ultimate disposal of low and medium radioactive waste in France  

SciTech Connect (OSTI)

The National Radioactive Waste Management Agency (ANDRA) has been entrusted with the long-term management of radioactive waste. This paper presents the methodology of safety assessment used by ANDRA for a land disposal facility of radioactive waste with short or medium half-life and with low or medium specific activity. This methodology was used in the design of ``the Centre de stockage de l`Aube``.

Ringeard, C. [National Radioactive Waste Management Agency, Fontenay aux Roses (France). Environmental, Safety, Quality Dept.

1993-12-31T23:59:59.000Z

294

Subseabed Disposal Program. Annual report, January-December 1978  

SciTech Connect (OSTI)

This is the fifth annual report describing the progress and evaluating the status of the Subseabed Disposal Program (SDP), which was begun in June 1973. The program was initiated by Sandia Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans.

Talbert, D.M. (ed.)

1980-02-01T23:59:59.000Z

295

Fort Saint Vrain HTGR (Th/U carbide) Fuel Characteristics for Disposal Criticality Analysis  

SciTech Connect (OSTI)

DOE-owned spent nuclear fuels encompass many fuel types. In an effort to facilitate criticality analysis for these various fuel types, they were categorized into eight characteristic fuel groups with emphasis on fuel matrix composition. Out of each fuel group, a representative fuel type was chosen for analysis as a bounding case within that fuel group. Generally, burnup data, fissile enrichments and total fuel mass govern the selection of the representative or candidate fuel within that group. For the HTGR group, the Fort Saint Vrain (FSV) reactor fuel has been chosen for the evaluation of viability for waste co-disposal. The FSV reactor was operated by Public Service of Colorado as a licensed power reactor. The FSV fuel employs a U/Th carbide matrix in individually pyrolytic carbon-coated particles. These individual particles are in turn coated with silicon carbide (SiC) and contained within fuel compacts, that are in turn embedded in graphite blocks that comprised the structural core of the reactor.

Taylor, Larry Lorin

2001-01-01T23:59:59.000Z

296

Personal Reflections on War and Sustainability  

E-Print Network [OSTI]

personal stories -- from "showering" with bottled water to teaching villagers to cook with solar ovens

Zhang, Junshan

297

Mined Geologic Disposal System Requirements Document. Revision 1  

SciTech Connect (OSTI)

This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS.

Not Available

1994-03-01T23:59:59.000Z

298

Proceedings of the 1981 subseabed disposal program. Annual workshop  

SciTech Connect (OSTI)

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

Not Available

1982-01-01T23:59:59.000Z

299

Disposal of Draeger Tubes at Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed.

Malik, N.P.

2000-10-13T23:59:59.000Z

300

Hanford land disposal restrictions plan for mixed wastes  

SciTech Connect (OSTI)

Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs.

Not Available

1990-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Pyramiding tumuli waste disposal site and method of construction thereof  

DOE Patents [OSTI]

An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

Golden, Martin P. (Hamburg, NY)

1989-01-01T23:59:59.000Z

302

Student Committee Representatives Guidelines Congratulations on being selected as a student representative to a GSLIS committee! We are  

E-Print Network [OSTI]

Student Committee Representatives Guidelines Congratulations on being selected as a student to your resume or CV. Your job is to represent students to committees and committees to students. You represent the student body to the committee. Your job is to advocate for your fellow students by bringing

Gilbert, Matthew

303

Student Assembly Offices Student Assembly Representatives: There are four representatives per class to the Student Assembly. Their duties are to  

E-Print Network [OSTI]

Student Assembly Offices Student Assembly Representatives: There are four representatives per class to the Student Assembly. Their duties are to: Represent the student body of the Medical College of Wisconsin-section of the student body. Fairly administer and distribute all funds including those designated as Student Activity

304

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.  

SciTech Connect (OSTI)

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the report, there was significant teaming between the various participants to best help the GOI. On-the-ground progress is the focus of the Iraq NDs Program and much of the work is a transfer of technical and practical skills and knowledge that Sandia uses day-to-day. On-the-ground progress was achieved in July of 2008 when the GOI began the physical cleanup and dismantlement of the Active Metallurgical Testing Laboratory (LAMA) facility at Al Tuwaitha, near Baghdad.

Cochran, John Russell; Danneels, Jeffrey John

2009-03-01T23:59:59.000Z

305

Does Dual Ownership of Waste Imply a Regional Disposal Approach?  

SciTech Connect (OSTI)

The construction of the Nuclear Power Plant Krsko, being located in Slovenia near the Slovenian-Croatian border, was a joint investment by Slovenia and Croatia, two republics of the former Yugoslavia. The plant was completed in 1981 and the commercial operation started early in 1983. The obligations and rights of both investors during the construction and operation were specified in two bilateral contracts signed in 1974 and 1982. These contracts were fairly detailed on construction, operation and exploitation of the nuclear power plant (NPP), but they said very little about future nuclear liabilities. The electricity production was equally shared between the two countries and both parties participated in management of the NPP. In 1991, after Slovenia and Croatia became two independent countries, the agreement on the ownership and exploitation of the NPP Krsko was re-negotiated and a new contract signed in 2003. By the new contract the decommissioning and the disposal of spent fuel (SF) as well as low and intermediate level waste (LILW) is the responsibility of both parties, and the financial resources for covering these liabilities should be equally provided. Regardless of shared ownership of waste, the agreement opts for a single disposal solution for LILW as well as for SF, but the details are left open. More clear elaboration of these responsibilities is given in the programme of the decommissioning and disposal of radioactive waste from the NPP which was jointly prepared by the Slovenian and Croatian waste management organisations in 2004. The programme is clearly opting for only one repository for LILW and one repository for spent fuel, which can be located either in Slovenia or Croatia. Irrespective of the country where such a repository will be sited, dual ownership of waste opens up another dimension of such a solution: will such a repository be regarded as a national facility or as a regional or multinational facility? Both options-national and regional/multinational- may have a strong influence on future agreements on waste disposal, but so far these aspects have not been addressed either in Slovenia or Croatia. The paper brings reflections and discussion on these aspects of waste management in Slovenia and reveals the current situation of the waste disposal project in the country. (authors)

Mele, I. [ARAO - Agency for Radwaste Management, Parmova 53, Si-1000 Ljubljana (Slovenia)

2006-07-01T23:59:59.000Z

306

Integrated Disposal Facility FY2010 Glass Testing Summary Report  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

2010-09-30T23:59:59.000Z

307

Soil Segregation Methods for Reducing Transportation and Disposal Costs - 13544  

SciTech Connect (OSTI)

At Formerly Utilized Sites Remedial Action Program (FUSRAP) sites where the selected alternative for contaminated soil is excavation and off-site disposal, the most significant budget items of the remedial action are the costs for transportation and disposal of soil at an off-site facility. At these sites, the objective is to excavate and dispose of only those soils that exceed derived concentration guideline levels. In situ soil segregation using gross gamma detectors to guide the excavation is often challenging at sites where the soil contamination is overlain by clean soil or where the contaminated soil is located in isolated, subsurface pockets. In addition, data gaps are often identified during the alternative evaluation and selection process, resulting in increased uncertainty in the extent of subsurface contamination. In response, the U.S. Army Corps of Engineers, Buffalo District is implementing ex situ soil segregation methods. At the remediated Painesville Site, soils were excavated and fed through a conveyor-belt system, which automatically segregated them into above- and below-cleanup criteria discharge piles utilizing gamma spectroscopy. At the Linde Site and the Shallow Land Disposal Area (SLDA) Site, which are both in the remediation phase, soils are initially segregated during the excavation process using gross gamma detectors and then transported to a pad for confirmatory manual surveying and sampling. At the Linde Site, the ex situ soils are analyzed on the basis of a site-specific method, to establish compliance with beneficial reuse criteria that were developed for the Linde remediation. At the SLDA Site, the ex situ soils are surveyed and sampled based on Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) final status survey guidance to demonstrate compliance with the derived concentration guideline levels. At all three sites, the ex situ soils that meet the site- specific DCGLs are retained on-site and used as backfill material. This paper describes the ex situ soil segregation methods, the considerations of each method, and the estimated cost savings from minimizing the volume of soil requiring transportation and off-site disposal. (authors)

Frothingham, David; Andrews, Shawn; Barker, Michelle; Boyle, James; Buechi, Stephen; Graham, Marc; Houston, Linda; Polek, Michael; Simmington, Robert; Spector, Harold [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States)] [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Elliott, Robert 'Dan' [U.S. Army Reserve, 812A Franklin St.,Worcester, MA 01604 (United States)] [U.S. Army Reserve, 812A Franklin St.,Worcester, MA 01604 (United States); 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

308

What is Personal Training? Personal Training offers a one-on-one  

E-Print Network [OSTI]

PERSONAL TRAINING What is Personal Training? Personal Training offers a one-on-one private workout program, your Personal Trainer will help you reach your goals. Learn the different weight training will begin your Personal Training program with a fitness assessment, which will give the trainer

McConnell, Terry

309

Containment and Analysis Capability Insights Gained from Drop Testing Representative Spent Nuclear Fuel Containers  

SciTech Connect (OSTI)

The National Spent Nuclear Fuel Program (NSNFP), operating from the Idaho National Engineering and Environmental Laboratory (INEEL), developed the standardized Department of Energy (DOE) spent nuclear fuel (SNF) canister. This canister is designed to be loaded with DOE SNF (including other radioactive materials) and then be used during interim storage, during transportation to the nations repository, and for final disposal at the repository without having to be reopened. The canister has been fully designed and has completed significant testing that clearly demonstrates that it can safely achieve its intended design goals. During 1999, nine 457-mm diameter test canisters were fabricated at the INEEL to represent the standardized DOE SNF canister design. Various "worst case" internals were incorporated. Seven of the test canisters were 4.57 m long and weighed approximately 2721 kg, while two were 3.00 m long and weighed approximately 1360 kg and 1725 kg. Seven of the test canisters were dropped from 9 m onto an essentially unyielding flat surface and one of the test canisters was dropped from 1 m onto a 15-cm diameter puncture post. The final test canister was dropped from 61 cm onto a 50.8 mm thick vertically oriented steel plate, and then fell over to impact another 50.8 mm thick vertically oriented steel plate. This last test represented a canister dropping onto another larger container such as a repository disposal container or waste package. The 1999 drop testing was performed at Sandia National Laboratories (SNL). The nine test canisters experienced varying degrees of damage to their skirts, lifting rings, and pressure boundary components (heads and main body). However, all of the canisters were shown to have maintained their pressure boundary (through pressure testing). Four heavily damaged canisters were also shown to be leaktight via helium leak testing. Pre- and post-drop finite element (FE) analyses were also performed. The results clearly indicated that accurate predictions of canister responses to the drop tests were achieved. The results achieved for the standardized canister can also be applicable to other well-constructed containers (canisters, casks, cans, vessels, etc.) subjected to similar loads. Properly designed containers can maintain a containment system after being subjected to dynamically induced high strains and FE computer analyses can accurately predict the resulting responses.

Morton, Dana Keith; Snow, Spencer David; Rahl, Tommy Ervin; Ware, Arthur Gates

2001-08-01T23:59:59.000Z

310

CCA-Treated wood disposed in landfills and life-cycle trade-offs with waste-to-energy and MSW landfill disposal  

E-Print Network [OSTI]

CCA-Treated wood disposed in landfills and life-cycle trade-offs with waste-to-energy and MSW in waste-to-energy (WTE) facilities. In other countries, the predominant disposal option for wood, others have not, and the product continues to enter the waste stream from construction, demolition

Florida, University of

311

4Q CY2001, Facility Representative Program Performance Indicators  

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

ID, seven Facility Representatives supported a two-week, around-the-clock assessment of conduct of operations at the Radioactive Waste Management Complex. The assessment provided...

312

4Q CY2000 (PDF), Facility Representative Program Performance...  

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

"The Facility Representative Program Performance Indicators Quarterly Report is attached, covering the period from October to December 2000. Data for these indicators are gathered...

313

General Engineer/Physical Scientist (Senior Facility Representative)  

Broader source: Energy.gov [DOE]

A successful candidate in this position will serve as the Site Managers Senior Facility Representative, and responsible for program management, technical monitoring, advising and evaluating all...

314

Reference Buildings by Climate Zone and Representative City:...  

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

A Minneapolis, Minnesota Reference Buildings by Climate Zone and Representative City: 6A Minneapolis, Minnesota In addition to the ZIP file for each building type, you can directly...

315

active demethylation represent: Topics by E-print Network  

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

Manager Meeting Representatives Environmental Sciences and Ecology Websites Summary: with security requirements associated with imaging, use only the DP form located at either of...

316

Appointment of Contracting Officers and Contracting Officer Representatives  

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

The Order established procedures governing the selection, appointment and termination of Department of Energy contracting officers and contracting officer representatives. Cancels DOE O 541.1A.

2004-04-21T23:59:59.000Z

317

Mobile Mapping and Personal Driving  

E-Print Network [OSTI]

-Computer Interaction Lab University of Maryland #12;Route Choice Matters Average driver spends a full week each year Custom annotation Enrich the data with personal notes Community and collaboration Fill in gaps tasks? Find the best route Find the best time to leave See which way other people go Add my own notes

Golbeck, Jennifer

318

Government Personal Property Asset Management  

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

To establish procedures for managing Government personal owned or leased by the Department of Energy (DOE) and in the custody of DOE Headquarters employees, including those in the National Nuclear Security Administration (NNSA), in accordance with Federal and Departmental regulations. Cancels HQ O 580.1.

2001-09-23T23:59:59.000Z

319

Headquarters Personal Property Asset Management  

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

To establish procedures for managing Government personal property owned or leased by the Department of Energy and in the custody of DOE Headquarters employees, including those in the National Nuclear Security Administration. Cancels DOE HQ O 580.1B. Canceled by DOE N 251.69.

2005-09-26T23:59:59.000Z

320

Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

French, Sean B. [Los Alamos National Laboratory; Shuman, Robert [WPS: WASTE PROJECTS AND SERVICES

2012-04-17T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Disposal of oil field wastes and NORM wastes into salt caverns.  

SciTech Connect (OSTI)

Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM), the risk to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne's research indicates that disposal of NOW into salt caverns is feasible and, in most cases, would not be prohibited by state agencies (although those agencies may need to revise their wastes management regulations). A risk analysis of several cavern leakage scenarios suggests that the risk from cavern disposal of NOW and NORM wastes is below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

Veil, J. A.

1999-01-27T23:59:59.000Z

322

Disposal of NORM-Contaminated Oil Field Wastes in Salt Caverns  

SciTech Connect (OSTI)

In 1995, the U.S. Department of Energy (DOE), Office of Fossil Energy, asked Argonne National Laboratory (Argonne) to conduct a preliminary technical and legal evaluation of disposing of nonhazardous oil field waste (NOW) into salt caverns. That study concluded that disposal of NOW into salt caverns is feasible and legal. If caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they can be a suitable means of disposing of NOW (Veil et al. 1996). Considering these findings and the increased U.S. interest in using salt caverns for NOW disposal, the Office of Fossil Energy asked Argonne to conduct further research on the cost of cavern disposal compared with the cost of more traditional NOW disposal methods and on preliminary identification and investigation of the risks associated with such disposal. The cost study (Veil 1997) found that disposal costs at the four permitted disposal caverns in the United States were comparable to or lower than the costs of other disposal facilities in the same geographic area. The risk study (Tomasko et al. 1997) estimated that both cancer and noncancer human health risks from drinking water that had been contaminated by releases of cavern contents were significantly lower than the accepted risk thresholds. Since 1992, DOE has funded Argonne to conduct a series of studies evaluating issues related to management and disposal of oil field wastes contaminated with naturally occurring radioactive material (NORM). Included among these studies were radiological dose assessments of several different NORM disposal options (Smith et al. 1996). In 1997, DOE asked Argonne to conduct additional analyses on waste disposal in salt caverns, except that this time the wastes to be evaluated would be those types of oil field wastes that are contaminated by NORM. This report describes these analyses. Throughout the remainder of this report, the term ''NORM waste'' is used to mean ''oil field waste contaminated by NORM''.

Blunt, D.L.; Elcock, D.; Smith, K.P.; Tomasko, D.; Viel, J.A.; and Williams, G.P.

1999-01-21T23:59:59.000Z

323

Design and Installation of a Disposal Cell Cover Field Test  

SciTech Connect (OSTI)

The U.S. Department of Energys Office of Legacy Management (LM) initiated a cover assessment project in September 2007 to evaluate an inexpensive approach to enhancing the hydrological performance of final covers for disposal cells. The objective is to accelerate and enhance natural processes that are transforming existing conventional covers, which rely on low-conductivity earthen barriers, into water balance covers, that store water in soil and release it as soil evaporation and plant transpiration. A low conductivity cover could be modified by deliberately blending the upper layers of the cover profile and planting native shrubs. A test facility was constructed at the Grand Junction, Colorado, Disposal Site to evaluate the proposed methodology. The test cover was constructed in two identical sections, each including a large drainage lysimeter. The test cover was constructed with the same design and using the same materials as the existing disposal cell in order to allow for a direct comparison of performance. One test section will be renovated using the proposed method; the other is a control. LM is using the lysimeters to evaluate the effectiveness of the renovation treatment by monitoring hydrologic conditions within the cover profile as well as all water entering and leaving the system. This paper describes the historical experience of final covers employing earthen barrier layers, the design and operation of the lysimeter test facility, testing conducted to characterize the as-built engineering and edaphic properties of the lysimeter soils, the calibration of instruments installed at the test facility, and monitoring data collected since the lysimeters were constructed.

Benson, C.H. [University of WisconsinMadison, Madison, Wisconsin; Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, Colorado; Albright, W.H. [Desert Research Institute, Reno, Nevada; Smith, G.M. [Geo-Smith Engineering, Grand Junction, Colorado; Bush, R.P. [U.S. Department of Energy, Grand Junction, Colorado

2011-02-27T23:59:59.000Z

324

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $311k in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R.; Wrights, R. S.

2002-02-25T23:59:59.000Z

325

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250-liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WlPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $3 1 lk in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R. (David R.); Wright, R. (Robert)

2002-01-01T23:59:59.000Z

326

Deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

2009-07-01T23:59:59.000Z

327

Representative well models for eight geothermal-resource areas  

SciTech Connect (OSTI)

Representative well models have been constructed for eight major geothermal-resource areas. The models define representative times and costs associated with the individual operations that can be expected during drilling and completion of geothermal wells. The models were made for and have been used to evaluate the impacts of potential new technologies. The nature, construction, and validation of the models are presented.

Carson, C.C.; Lin, Y.T.; Livesay, B.J.

1983-02-01T23:59:59.000Z

328

Update on onshore disposal of offshore drilling wastes  

SciTech Connect (OSTI)

The US Environmental Protection Agency (EPA) is developing effluent limitations guidelines to govern discharges of cuttings from wells drilled using synthetic-based muds. To support this rulemaking, Argonne National Laboratory was asked by EPA and the US Department of Energy (DOE) to collect current information about those onshore commercial disposal facilities that are permitted to receive offshore drilling wastes. Argonne contacted state officials in Louisiana, Texas, California and Alaska to obtain this information. The findings, collected during October and November 1999, are presented by state.

Veil, J. A.

1999-11-29T23:59:59.000Z

329

Disposable Vacuum Viewport Protector | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed Newcatalyst phasesDataTranslocation oftheAmperometric Detection ofDisposable Vacuum

330

Title I Disposal Sites Annual Report | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy Usage »of EnergyThe EnergyDepartment7 th , 2007Timothy RunyonTitle I Disposal

331

SENSITIVITY ANALYSIS FOR SALTSTONE DISPOSAL UNIT COLUMN DEGRADATION ANALYSES  

SciTech Connect (OSTI)

PORFLOW related analyses supporting a Sensitivity Analysis for Saltstone Disposal Unit (SDU) column degradation were performed. Previous analyses, Flach and Taylor 2014, used a model in which the SDU columns degraded in a piecewise manner from the top and bottom simultaneously. The current analyses employs a model in which all pieces of the column degrade at the same time. Information was extracted from the analyses which may be useful in determining the distribution of Tc-99 in the various SDUs throughout time and in determining flow balances for the SDUs.

Flach, G.

2014-10-28T23:59:59.000Z

332

Disposal Practices at the Nevada Test Site 2008  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat Pump Models |Conduct, Parent(CRADA and DOW Area 5 LLRW & MLLW Disposal ETR

333

DOE - Office of Legacy Management -- Pennsylvania Disposal Site - PA 43  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are herePAOsborne Co - OH 34PantexDisposal Site - PA

334

Low-Level Waste Disposal Facility Federal Review Group Manual  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | DepartmentEnergy InvitationLegaltoLizLow- LEVEL WASTE DISPOSAL FACILITY

335

Personal Property (Informational Purposes Only)  

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

This draft has been scheduled for final review before the Directives Review Board on 02/5/2015. All major comments and concerns should be provided to your DRB representative by 02/3/2015, following your organization process. If you do not know who your representative is, please see the list of DRB members. If your office is represented by Ingrid Kolb, Director, Office of Management, please submit your major concerns and comments to the DRB Liaison, Camille Beben (Camille.Beben@hq.doe.gov; 202-586-1014).

2015-01-26T23:59:59.000Z

336

Incipient toxicity of lithium to freshwater organisms representing a salmonid habitat  

SciTech Connect (OSTI)

Because the eventual development of fusion power reactors could increase the mining, use and disposal of lithium five-fold by the year 2000, potential effects from unusual amounts of lithium in aquatic environments were investigated. Freshwater oganisms representing a Pacific Northwest salmonid habitat were exposed to elevated conentrations of lithium. Nine parameters were used to determine the incipient toxicity of lithium to rainbow trout (Salmo gairdneri), insect larvae (Chironomus sp.), and Columbia River periphyton. All three groups of biota were incipiently sensitive to lithium at concentrations ranging between 0.1 and 1 mg/L. These results correspond with the incipient toxicity of beryllium, a chemically similar component of fusion reactor cores. A maximum lithium concentration of 0.01 mg/L occurs naturally in most freshwater environments (beryllium is rarer). Therefore, a concentration range of 0.01 to 0.1 mg/L may be regarded as approaching toxic concentrations when assessing the hazards of lithium in freshwaters.

Emery, R.; Klopfer, D.C.; Skalski, J.R.

1981-07-01T23:59:59.000Z

337

Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139.

Grant Evenson

2006-04-01T23:59:59.000Z

338

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2014-06-01T23:59:59.000Z

339

Overview of Low-Level Waste Disposal Operations at the Nevada Test Site  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future.

DOE /Navarro

2007-02-01T23:59:59.000Z

340

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-04-01T23:59:59.000Z

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341

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-01-01T23:59:59.000Z

342

The Texas Solution to the Nation's Disposal Needs for Irradiated Hardware - 13337  

SciTech Connect (OSTI)

The closure of the disposal facility in Barnwell, South Carolina, to out-of-compact states in 2008 left commercial nuclear power plants without a disposal option for Class B and C irradiated hardware. In 2012, Waste Control Specialists LLC (WCS) opened a highly engineered facility specifically designed and built for the disposal of Class B and C waste. The WCS facility is the first Interstate Compact low-level radioactive waste disposal facility to be licensed and operated under the Low-level Waste Policy Act of 1980, as amended in 1985. Due to design requirements of a modern Low Level Radioactive Waste (LLRW) facility, traditional methods for disposal were not achievable at the WCS site. Earlier methods primarily utilized the As Low as Reasonably Achievable (ALARA) concept of distance to accomplish worker safety. The WCS method required the use of all three ALARA concepts of time, distance, and shielding to ensure the safe disposal of this highly hazardous waste stream. (authors)

Britten, Jay M. [Waste Control Specialists LLC, Andrews, TX 79714 (United States)] [Waste Control Specialists LLC, Andrews, TX 79714 (United States)

2013-07-01T23:59:59.000Z

343

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities.

Porter, C.L.; Widmayer, D.A.

1995-09-01T23:59:59.000Z

344

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-04-01T23:59:59.000Z

345

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-06-01T23:59:59.000Z

346

WVU Personal Rapid Transit Benefit Cost Analysis  

E-Print Network [OSTI]

WVU Personal Rapid Transit Benefit Cost Analysis Morgantown, West Virginia Prepared For: West ......................................................................... 12 Demographic Data Summary techniques suitable for assessing the impact of the WVU Personal Rapid Transit System (PRT) was employed

Mohaghegh, Shahab

347

Department of Energy Personal Property Management Program  

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

This Order provides responsibilities and requirements for personal property management at the Department. Change 1, dated 5-8-08, includes responsibilities for heads of Departmental elements to be accountable for personal property inventories.

2005-12-07T23:59:59.000Z

348

Department of Energy Personal Property Management Program  

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

This Order provides responsibilities and requirements for personal property management at the Department. Change 1, dated 5-8-08, includes responsibilities for heads of Departmental elements to be accountable for personal property inventories. Cancels DOE O 580.1.

2005-12-07T23:59:59.000Z

349

Assessing Effectiveness of Personality Style in Documentation  

E-Print Network [OSTI]

interfaces Training, help and documentation, theory and methods. General Terms Documentation ManagementAssessing Effectiveness of Personality Style in Documentation Kenneth Sayles. Department conducted a similar experiment, but looking beyond preference to see if the personality of documentation

Novick, David G.

350

Behavior-based personalization : strategies and Implications  

E-Print Network [OSTI]

The personalization of services and products offered to customers is becoming crucial for the success of companies. Firms that can maintain a personalized relationship with their customers will not only gain an advantage ...

Violante, Joo G

2011-01-01T23:59:59.000Z

351

SIGN HERE : informed consent in personalized medicine  

E-Print Network [OSTI]

The next era of medicine will be one of personalization, scientists and physicians promise. Personalized medicine is a refined clinical approach in which clinicians will utilize your genomic information to help you prevent ...

Ahmed, Abdul-Kareem H

2013-01-01T23:59:59.000Z

352

Low-level radioactive waste disposal facility closure  

SciTech Connect (OSTI)

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

353

The Suitable Geological Formations for Spent Fuel Disposal in Romania  

SciTech Connect (OSTI)

Using the experience in the field of advanced countries and formerly Romanian program data, ANDRAD, the agency responsible for the disposal of radioactive wastes, started the program for spent fuel disposal in deep geological formations with a documentary analysis at the national scale. The potential geological formations properly characterized elsewhere in the world: salt, clay, volcanic tuff, granite and crystalline rocks,. are all present in Romania. Using general or specific selection criteria, we presently consider the following two areas for candidate geological formations: 1. Clay formations in two areas in the western part of Romania: (1) The Pannonian basin Socodor - Zarand, where the clay formation is 3000 m thick, with many bentonitic strata and undisturbed structure, and (2) The Eocene Red Clay on the Somes River, extending 1200 m below the surface. They both need a large investigation program in order to establish and select the required homogeneous, dry and undisturbed zones at a suitable depth. 2. Old platform green schist formations, low metamorphosed, quartz and feldspar rich rocks, in the Central Dobrogea structural unit, not far from Cernavoda NPP (30 km average distance), 3000 m thick and including many homogeneous, fine granular, undisturbed, up to 300 m thick layers. (authors)

Marunteanu, C. [Bucharest Univ. (Romania); Ionita, G. [ANDRAD, Bucharest (Romania); Durdun, I. [S.C. GEOTEC S.A., Bucharest (Romania)

2007-07-01T23:59:59.000Z

354

Oil field waste disposal in salt caverns: An information website  

SciTech Connect (OSTI)

Argonne National Laboratory has completed the construction of a Website for the US Department of Energy (DOE) that provides detailed information on salt caverns and their use for disposing of nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM). Specific topics in the Website include the following: descriptions of salt deposits and salt caverns within the US, salt cavern construction methods, potential types of wastes, waste emplacement, regulatory issues, costs, carcinogenic and noncarcinogenic human health risks associated with postulated cavern release scenarios, new information on cavern disposal (e.g., upcoming meetings, regulatory issues, etc.), other studies supported by the National Petroleum Technology Office (NPTO) (e.g., considerations of site location, cavern stability, development issues, and bedded salt characterization in the Midland Basin), and links to other associated Web sites. In addition, the Website allows downloadable access to reports prepared on the topic that were funded by DOE. Because of the large quantities of NOW and NORM wastes generated annually by the oil industry, information presented on this Website is particularly interesting and valuable to project managers, regulators, and concerned citizens.

Tomasko, D.; Veil, J. A.

1999-12-10T23:59:59.000Z

355

Performance assessment for the class L-II disposal facility  

SciTech Connect (OSTI)

This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

NONE

1997-03-01T23:59:59.000Z

356

Plans and Progress on Hanford MLLW Treatment and Disposal  

SciTech Connect (OSTI)

Mixed low-level waste (MLLW) contains both low-level radioactive materials and low-level hazardous chemicals. The hazardous component of mixed waste has characteristics identified by any or all of the following statutes: the Resource Conservation and Recovery Act of 1976 (RCRA), as amended; the Toxic Substances Control Act of 1976; and Washington State dangerous waste regulations. The Fluor Hanford Waste Management Project (WMP) is responsible for storing, treating, and disposing of solid MLLW, which includes organic and inorganic solids, organics and inorganic lab packs, debris, lead, mercury, long-length equipment, spent melters, and remote-handled (RH) and oversized MLLW. Hanford has 7,000 cubic meters, or about 25%, of the MLLW in storage at U.S. Department of Energy (DOE) sites. Hanford plans to receive 57,000 cubic meters from on-site generators, or about 50% of DOE's newly generated MLLW. In addition, the Hanford Environment Restoration Program and off-site generators having approved Federal Facility Consent Agreement site treatment plans will most likely send 200 cubic meters of waste to be treated and returned to the generators. Volumes of off-site waste receipts will be affected when the MLLW Record of Decision is issued as part of the process for the Hanford Site Solid Waste Environmental Impact Statement (EIS). The WMP objective relative to MLLW is to treat and dispose of {approx}8000 cubic meters of existing inventory and newly-generated waste by September 30, 2006.

McDonald, K. M.; Blackford, L. T.; Nester, D. E.; Connolly, R. R.; McKenney, D. E.; Moy, S. K.

2003-02-24T23:59:59.000Z

357

Use and disposal of waste-water sludge in Illinois. Final report  

SciTech Connect (OSTI)

The United States Environmental Protection Agency (USEPA) proposed Part 503 Rules on sludge were first published in February 1989. Part 503 proposed sludge regulations address five categories of sludge use or disposal: land application, distribution and marketing, monofills, surface disposal sites, and incineration. The report on sludge management in Illinois examines the probable effects that the proposed federal rules on use and disposal of sewage sludge will have on current practices by Illinois publicly owned treatment works outside the City of Chicago.

John, S.F.; Kane, D.N.; Hinesly, T.D.

1992-02-01T23:59:59.000Z

358

International low level waste disposal practices and facilities  

SciTech Connect (OSTI)

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of options for the management of radioactive waste. There is a variety of alternatives for processing waste and for short term or long term storage prior to disposal. Likewise, there are various alternatives currently in use across the globe for the safe disposal of waste, ranging from near surface to geological disposal, depending on the specific classification of the waste. At present, there appears to be a clear and unequivocal understanding that each country is ethically and legally responsible for its own wastes, in accordance with the provisions of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Therefore the default position is that all nuclear wastes will be disposed of in each of the 40 or so countries concerned with nuclear power generation or part of the fuel cycle. To illustrate the global distribution of radioactive waste now and in the near future, Table 1 provides the regional breakdown, based on the UN classification of the world in regions illustrated in Figure 1, of nuclear power reactors in operation and under construction worldwide. In summary, 31 countries operate 433 plants, with a total capacity of more than 365 gigawatts of electrical energy (GW[e]). A further 65 units, totaling nearly 63 GW(e), are under construction across 15 of these nations. In addition, 65 countries are expressing new interest in, considering, or actively planning for nuclear power to help address growing energy demands to fuel economic growth and development, climate change concerns, and volatile fossil fuel prices. Of these 65 new countries, 21 are in Asia and the Pacific region, 21 are from the Africa region, 12 are in Europe (mostly Eastern Europe), and 11 in Central and South America. However, 31 of these 65 are not currently planning to build reactors, and 17 of those 31 have grids of less than 5 GW, which is said to be too small to accommodate most of the reactor designs available. For the remaining 34 countries actively planning reactors, as of September 2010: 14 indicate a strong intention to precede w

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19T23:59:59.000Z

359

System-Level Logistics for Dual Purpose Canister Disposal  

SciTech Connect (OSTI)

The analysis presented in this report investigated how the direct disposal of dual purpose canisters (DPCs) may be affected by the use of standard transportation aging and disposal canisters (STADs), early or late start of the repository, and the repository emplacement thermal power limits. The impacts were evaluated with regard to the availability of the DPCs for emplacement, achievable repository acceptance rates, additional storage required at an interim storage facility (ISF) and additional emplacement time compared to the corresponding repackaging scenarios, and fuel age at emplacement. The result of this analysis demonstrated that the biggest difference in the availability of UNF for emplacement between the DPC-only loading scenario and the DPCs and STADs loading scenario is for a repository start date of 2036 with a 6 kW thermal power limit. The differences are also seen in the availability of UNF for emplacement between the DPC-only loading scenario and the DPCs and STADs loading scenario for the alternative with a 6 kW thermal limit and a 2048 start date, and for the alternatives with a 10 kW thermal limit and 2036 and 2048 start dates. The alternatives with disposal of UNF in both DPCs and STADs did not require additional storage, regardless of the repository acceptance rate, as compared to the reference repackaging case. In comparison to the reference repackaging case, alternatives with the 18 kW emplacement thermal limit required little to no additional emplacement time, regardless of the repository start time, the fuel loading scenario, or the repository acceptance rate. Alternatives with the 10 kW emplacement thermal limit and the DPCs and STADs fuel loading scenario required some additional emplacement time. The most significant decrease in additional emplacement time occurred in the alternative with the 6 kW thermal limit and the 2036 repository starting date. The average fuel age at emplacement ranges from 46 to 88 years. The maximum fuel age at emplacement ranges from 81 to 146 years. The difference in the average and maximum age of fuel at emplacement between the DPC-only and the DPCs and STADs fuel loading scenarios becomes less significant as the repository thermal limit increases and as the repository start date increases. In general, the role of STADs is to store young (30 year or younger) high burnup (45 GWD/MTU or higher) fuel. Recommendations for future study include detailed evaluation of the feasible alternatives with regard to the costs and factors not considered in this analysis, such as worker dose, dose to members of the public, and economic benefits to host entities. It is also recommended to conduct an additional analysis to evaluate the assumption regarding the transportability and disposability of DPCs for the next iteration of the direct disposal of DPCs study.

Kalinina, Elena A.

2014-06-03T23:59:59.000Z

360

Department of Energy Personal Property Management Program  

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

The order sets forth requirements for personal property management and accountability. Admin Chg 1, dated 10-22-12.

2012-03-30T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Agency and First-Person Authority  

E-Print Network [OSTI]

Thesis without undermining the epistemic distinctiveness of first-person access. I According to Shoemaker, a self-blind

Parrott, Matthew Thomas

2011-01-01T23:59:59.000Z

362

Internally Displaced Persons in Nepal  

E-Print Network [OSTI]

Peace and Democracy in South Asia, Volume 1, Issue 2, 2005. Bandana Shrestha has been volunteering with the Nepal Institute of Peace, Kathmandu, as Programme Coordinator. Her email ID is: shrestha_bandana@yahoo.com. Som Niroula is Programme... Officer of the Nepal Institute of Peace. Email: niroulasom@yahoo.com. Internally Displaced Persons in Nepal BANDANA SHRESTHA & SOM NIROULA Background Nepal has been in an internal armed conflict since 1996 between the Communist Party...

Shrestha, Bandana; Niroula, Som

2005-01-01T23:59:59.000Z

363

Pluggable Personal Data Servers Nicolas Anciaux*  

E-Print Network [OSTI]

Pluggable Personal Data Servers Nicolas Anciaux* , Luc Bouganim* , Yanli Guo* , Philippe Pucheral, France @gemalto.com ABSTRACT An increasing amount of personal data is automatically gathered, introduces a credible alternative to the systematic centralization of personal data. By embedding a full

Paris-Sud XI, Université de

364

PERSONAL DATA (IT0002) Mr. Miss Dr.  

E-Print Network [OSTI]

Update PERSONAL DATA (IT0002) Mr. Miss Dr. Gender Male Female State Complete Information No Address OF TENNESSEE PERSONAL DATA FORM Personnel # PERMANENT RESIDENCE (IT0006-Subtype 1) Form of Address: New Ms Code PDF Rev. 03/20/2008 Page 1 of 2 #12;ADDITIONAL PERSONAL DATA (IT0077) Yes Yes No Employee

Tennessee, University of

365

Personal Finance Make Your Money Matter  

E-Print Network [OSTI]

Personal Finance Make Your Money Matter Name: Registration number: Department: Year of study of your portfolio. #12;Personal Finance Make Your Money Matter2 Contents Timetable Page 3 Introduction 16 #12;Personal Finance Make Your Money Matter3 Timetable Friday 6.00 pm Introduction

Stevenson, Mark

366

Device Selection by a Personal Proxy Agent  

E-Print Network [OSTI]

Device Selection by a Personal Proxy Agent N. Hadibi, K. El-khatib, Eric Z. Zhang, Ken Chan, G. v user to access communication devices currently present in his Personal Area Network (PAN) Performs PreferencesDevice Capability An example Scenario: Connecting Alice and Bob w/o a Personal Proxy Internet Home

von Bochmann, Gregor

367

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513  

SciTech Connect (OSTI)

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

368

Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the US Department of Energy (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. The US Nuclear Regulatory Commission (NRC) developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Burro Canyon disposal cell. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete at the Burro Canyon disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. Ground water monitoring will not be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low yield from the uppermost aquifer.

NONE

1998-05-01T23:59:59.000Z

369

Technical support document for the surface disposal of sewage sludge. Final report  

SciTech Connect (OSTI)

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed.

Not Available

1992-11-01T23:59:59.000Z

370

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

SciTech Connect (OSTI)

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

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

1996-06-01T23:59:59.000Z

371

[Composite analysis E-area vaults and saltstone disposal facilities]. PORFLOW and FACT input files  

SciTech Connect (OSTI)

This diskette contains the PORFLOW and FACT input files described in Appendix B of the accompanying report `Composite Analysis E-Area Vaults and Saltstone Disposal Facilities`.

Cook, J.R.

1997-09-01T23:59:59.000Z

372

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-05-01T23:59:59.000Z

373

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-10-01T23:59:59.000Z

374

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-02-01T23:59:59.000Z

375

E-Print Network 3.0 - additional llrw disposal Sample Search...  

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

of Biological and Ecological Engineering, Oregon State University Collection: Environmental Sciences and Ecology 3 CO-DISPOSAL FACILITY FOR HAZARDOUS AND LOW-LEVEL...

376

Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous...  

Office of Environmental Management (EM)

risks associated with worker safety and the environment (e.g., resource consumption, air pollution, air dispersal) that may be associated with exhumation and re-disposal of...

377

SUPERCOMPUTER EDUCATION AND RESEARCH CENTER LIST OF ITEMS FOR DISPOSAL  

E-Print Network [OSTI]

Machine 35. Water Chiller Unit 36. Assorted Circuit Boards 37. Various type of Power Supply 38. Keyboards. Ungermann Bass ­ Network Items 20. Personal Computers (CPU only) #12;21. Laptop/Think Pads 22. Heavy Duty Line Printers 23. Heavy Duty Laser Printers 24. Heavy Duty Colour Laser Printers 25. HP Draft Masters

Govindarajan, Ramaswamy

378

A risk-based decision-aiding tool for waste disposal  

SciTech Connect (OSTI)

N-CART (the National Spent Nuclear Fuel Program Cost Analysis and Risk Tool) is being developed to aid in low-risk, cost-effective, timely management of radioactive waste and spent nuclear fuel, and can therefore be used in management of mixed waste. N-CART provides evaluation of multiple alternatives and presents the consequences of proposed waste management activities in a clear and concise format. N-CART`s decision-aiding analyses include comparisons and sensitivity analyses of multiple alternatives and allows the user to perform quick turn-around {open_quotes}what if{close_quotes} studies to investigate various scenarios. Uncertainties in data (such as cost and schedule of various activities) are represented as distributions. N-CART centralizes documentation of the bases of program alternatives and program decisions, thereby supporting responses to stakeholders concerns. The initial N-CART design considers regulatory requirements, costs, and schedules for alternative courses of action. The final design will include risks (public health, occupational, economic, scheduling), economic benefits, and the impacts of secondary waste generation. An optimization tool is being incorporated that allows the user to specify the relative importance of cost, time risks, and other bases for decisions. The N-CART prototype can be used to compare the costs and schedules of disposal alternatives for mixed low-level radioactive waste (MLLW) and greater-than-Class-C (GTCC) waste, as well as spent nuclear fuel (SNF) and related scrap material.

Weiner, R.F.; Reiser, A.S. [Sandia National Labs., Albuquerque, NM (United States); Elcock, C.G.; Nevins, S. [Los Alamos Technical Associates, Albuquerque, NM (United States)

1997-10-01T23:59:59.000Z

379

Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

This data package documents the experimentally derived input data on the representative waste glasses; LAWA44, LAWB45, and LAWC22. This data will be used for Subsurface Transport Over Reactive Multi-phases (STORM) simulations of the Integrated Disposal Facility (IDF) for immobilized low-activity waste (ILAW). The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in July 2005. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali (Na+)-hydrogen (H+) ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow (PUF) and product consistency (PCT) tests where used for accelerated weathering or aging of the glasses in order to determine a chemical reaction network of secondary phases that form. The majority of the thermodynamic data used in this data package were extracted from the thermody-namic database package shipped with the geochemical code EQ3/6, version 8.0. Because of the expected importance of 129I release from secondary waste streams being sent to IDF from various thermal treatment processes, parameter estimates for diffusional release and solubility-controlled release from cementitious waste forms were estimated from the available literature.

Pierce, Eric M.; McGrail, B. Peter; Rodriguez, Elsa A.; Schaef, Herbert T.; Saripalli, Prasad; Serne, R. Jeffrey; Krupka, Kenneth M.; Martin, P. F.; Baum, Steven R.; Geiszler, Keith N.; Reed, Lunde R.; Shaw, Wendy J.

2004-09-01T23:59:59.000Z

380

Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada  

SciTech Connect (OSTI)

Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation`s first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey`s continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base.

Carr, M.D.; Yount, J.C. (eds.)

1988-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

*Official Academic Senate Representative Dean of UC Davis Extension  

E-Print Network [OSTI]

*Official Academic Senate Representative Dean of UC Davis Extension Recruitment Advisory Committee, Health Sciences, Public Policy & Business Programs, UC Davis Extension Chloe Fox Undergraduate Student, International Agricultural Development; Outreach Coordinator, Program for International Energy Technologies

Schladow, S. Geoffrey

382

Changes to the Facility Representative Program, 10/26/1999  

Broader source: Energy.gov [DOE]

Effective October 1, 1999, the Deputy Secretary tasked this office to manage the Facility Representative Program. We look forward to working with you in continuing and improving this very important...

383

Appointment of Contracting Officers and Contracting Officer Representatives  

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

To establish procedures governing the selection, appointment, and termination of contracting officers and for the appointment of contracting officer representatives. Cancels DOE Order 4200.4A. Canceled by DOE O 541.1A.

1996-04-30T23:59:59.000Z

384

Reference Buildings by Climate Zone and Representative City:...  

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

1A Miami, Florida Reference Buildings by Climate Zone and Representative City: 1A Miami, Florida In addition to the ZIP file for each building type, you can directly view the...

385

Reference Buildings by Climate Zone and Representative City:...  

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

B Boulder, Colorado Reference Buildings by Climate Zone and Representative City: 5B Boulder, Colorado In addition to the ZIP file for each building type, you can directly view the...

386

Reference Buildings by Climate Zone and Representative City:...  

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

A Chicago, Illinois Reference Buildings by Climate Zone and Representative City: 5A Chicago, Illinois In addition to the ZIP file for each building type, you can directly view the...

387

Reference Buildings by Climate Zone and Representative City:...  

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

B Phoenix, Arizona Reference Buildings by Climate Zone and Representative City: 2B Phoenix, Arizona In addition to the ZIP file for each building type, you can directly view the...

388

Reference Buildings by Climate Zone and Representative City:...  

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

7 Duluth, Minnesota Reference Buildings by Climate Zone and Representative City: 7 Duluth, Minnesota In addition to the ZIP file for each building type, you can directly view the...

389

Reference Buildings by Climate Zone and Representative City:...  

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

A Baltimore, Maryland Reference Buildings by Climate Zone and Representative City: 4A Baltimore, Maryland In addition to the ZIP file for each building type, you can directly view...

390

Reference Buildings by Climate Zone and Representative City:...  

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

C Seattle, Washington Reference Buildings by Climate Zone and Representative City: 4C Seattle, Washington In addition to the ZIP file for each building type, you can directly view...

391

Reference Buildings by Climate Zone and Representative City:...  

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

A Atlanta, Georgia Reference Buildings by Climate Zone and Representative City: 3A Atlanta, Georgia In addition to the ZIP file for each building type, you can directly view the...

392

Reference Buildings by Climate Zone and Representative City:...  

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

8 Fairbanks, Alaska Reference Buildings by Climate Zone and Representative City: 8 Fairbanks, Alaska In addition to the ZIP file for each building type, you can directly view the...

393

Reference Buildings by Climate Zone and Representative City:...  

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

B Las Vegas, Nevada Reference Buildings by Climate Zone and Representative City: 3B Las Vegas, Nevada In addition to the ZIP file for each building type, you can directly view the...

394

Reference Buildings by Climate Zone and Representative City:...  

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

A Houston, Texas Reference Buildings by Climate Zone and Representative City: 2A Houston, Texas In addition to the ZIP file for each building type, you can directly view the...

395

Reference Buildings by Climate Zone and Representative City:...  

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

B Helena, Montana Reference Buildings by Climate Zone and Representative City: 6B Helena, Montana In addition to the ZIP file for each building type, you can directly view the...

396

Reference Buildings by Climate Zone and Representative City:...  

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

C San Francisco, California Reference Buildings by Climate Zone and Representative City: 3C San Francisco, California In addition to the ZIP file for each building type, you can...

397

Reference Buildings by Climate Zone and Representative City:...  

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

B Los Angeles, California Reference Buildings by Climate Zone and Representative City: 3B Los Angeles, California In addition to the ZIP file for each building type, you can...

398

August 20, 2014 meeting with DOE representatives regarding the...  

Energy Savers [EERE]

August 20, 2014 meeting with DOE representatives regarding the remand of the DOE Direct Final Rule as it relates to efficiency standards for non-weatherized gas furnaces August 20,...

399

A representative individual from Arrovian aggregation of parametric individual utilities  

E-Print Network [OSTI]

A representative individual from Arrovian aggregation of parametric individual utilities social choice theory Assumptions Assumption on decisive coalitions Assumptions on individual utility functions Assumptions on the social welfare function Results The socially acceptable utility function

400

Department of Defense Representatives Visit Hanford to Benchmark Safety  

Broader source: Energy.gov [DOE]

RICHLAND, Wash., December 16, 2005, Representatives of the Department of Defense's (DoD's) Voluntary Protection Program Center of Excellence (VPP CX) working to reduce injuries at selected (DoD)...

Note: This page contains sample records for the topic "representing disposable personal" 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

Reference Buildings by Climate Zone and Representative City:...  

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

B Albuquerque, New Mexico Reference Buildings by Climate Zone and Representative City: 4B Albuquerque, New Mexico In addition to the ZIP file for each building type, you can...

402

Student personal information: your personal data (Student Information Privacy notice -fair processing statement)  

E-Print Network [OSTI]

Student personal information: your personal data (Student Information Privacy notice -fair personal data In accordance with the Data Protection Act 1998, Heriot-Watt University is registered as the Data Controller for personal data we hold about you. The University collects and processes information

Greenaway, Alan

403

Personality Traits, Personality Disorder Dimensions, and Physical Health: The Predictive Ability of Self and Informant Reports  

E-Print Network [OSTI]

Informant-reported Physical Health .......................................................................................... 72 1 CHAPTER I INTRODUCTION As Allport (1937) famously stated, personality is something and personality does... something (p. 48). What does personality do? Personality affects (and is affected by) ones happiness and subjective well-being, physical health and longevity, mental health, interpersonal relationships, and occupational success (see Ozer & Benet...

Cooper, Luke D

2014-04-24T23:59:59.000Z

404

Deep Geologic Nuclear Waste Disposal - No New Taxes - 12469  

SciTech Connect (OSTI)

To some, the perceived inability of the United States to dispose of high-level nuclear waste justifies a moratorium on expansion of nuclear power in this country. Instead, it is more an example of how science yields to social pressure, even on a subject as technical as nuclear waste. Most of the problems, however, stem from confusion on the part of the public and their elected officials, not from a lack of scientific knowledge. We know where to put nuclear waste, how to put it there, how much it will cost, and how well it will work. And it's all about the geology. The President's Blue Ribbon Commission on America's Nuclear Future has drafted a number of recommendations addressing nuclear energy and waste issues (BRC 2011) and three recommendations, in particular, have set the stage for a new strategy to dispose of high-level nuclear waste and to manage spent nuclear fuel in the United States: 1) interim storage for spent nuclear fuel, 2) resumption of the site selection process for a second repository, and 3) a quasi-government entity to execute the program and take control of the Nuclear Waste Fund in order to do so. The first two recommendations allow removal and storage of spent fuel from reactor sites to be used in the future, and allows permanent disposal of actual waste, while the third controls cost and administration. The Nuclear Waste Policy Act of 1982 (NPWA 1982) provides the second repository different waste criteria, retrievability, and schedule, so massive salt returns as the candidate formation of choice. The cost (in 2007 dollars) of disposing of 83,000 metric tons of heavy metal (MTHM) high-level waste (HLW) is about $ 83 billion (b) in volcanic tuff, $ 29 b in massive salt, and $ 77 b in crystalline rock. Only in salt is the annual revenue stream from the Nuclear Waste Fund more than sufficient to accomplish this program without additional taxes or rate hikes. The cost is determined primarily by the suitability of the geologic formation, i.e., how well it performs on its own for millions of years with little engineering assistance from humans. It is critical that the states most affected by this issue (WA, SC, ID, TN, NM and perhaps others) develop an independent multi-state agreement in order for a successful program to move forward. Federal approval would follow. Unknown to most, the United States has a successful operating deep permanent geologic nuclear repository for high and low activity waste, called the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Its success results from several factors, including an optimal geologic and physio-graphic setting, a strong scientific basis, early regional community support, frequent interactions among stakeholders at all stages of the process, long-term commitment from the upper management of the U.S. Department of Energy (DOE) over several administrations, strong New Mexico State involvement and oversight, and constant environmental monitoring from before nuclear waste was first emplaced in the WIPP underground (in 1999) to the present. WIPP is located in the massive bedded salts of the Salado Formation, whose geological, physical, chemical, redox, thermal, and creep-closure properties make it an ideal formation for long-term disposal, long-term in this case being greater than 200 million years. These properties also mean minimal engineering requirements as the rock does most of the work of isolating the waste. WIPP has been operating for twelve years, and as of this writing, has disposed of over 80,000 m{sup 3} of nuclear weapons waste, called transuranic or TRU waste (>100 nCurie/g but <23 Curie/1000 cm{sup 3}) including some high activity waste from reprocessing of spent fuel from old weapons reactors. All nuclear waste of any type from any source can be disposed in this formation better, safer and cheaper than in any other geologic formation. At the same time, it is critical that we complete the Yucca Mountain license application review so as not to undermine the credibility of the Nuclear Regulatory Commission and the scientific commun

Conca, James [RJLee Group, Inc., Pasco WA 509.205.7541 (United States); Wright, Judith [UFA Ventures, Inc., Richland, WA (United States)

2012-07-01T23:59:59.000Z

405

Enhancing RESRAD-OFFSITE for Low Level Waste Disposal Facility Performance Assessment  

Broader source: Energy.gov [DOE]

Abstract: The RESRAD-OFFSITE code was developed to evaluate the radiological dose and excess cancer risk to an individual who is exposed while located within or outside the area of initial (primary) contamination. The primary contamination, which is the source of all releases modeled by the code, is assumed to be a layer of soil. The code considers the release of contamination from the source to the atmosphere, to surface runoff, and to groundwater. The radionuclide leaching was modeled as a first order (without transport) release using radionuclide distribution coefficient and infiltration rate calculated from water balance (precipitation, surface runoff, evapotranspiration, etc.). Recently, a new source term model was added the RESRAD-OFFSITE code so that it can be applied to the evaluation of Low Level Waste (LLW) disposal facility performance assessment. This new improved source term model include (1) first order with transport, (2) equilibrium desorption (rinse) release, and (3) uniform release (constant dissolution). With these new source release options, it is possible to simulate both uncontainerized (soil) contamination and containerized (waste drums) contamination. A delay time in the source release was also added to the code. This allows modeling the LLW container degradation as a function of time. The RESRAD-OFFSITE code also allows linking to other codes using improved flux and concentration input options. Additional source release model such as diffusion release may be added later. In addition, radionuclide database with 1252 radionuclides (ICRP 107) and the corresponding dose coefficients (DCFPAK 3.02) and the Department of Energys new gender- and age-averaged Reference Person dose coefficients (DOE-STD-1196-2011) which is based on the US census data will be added to the next version of RESRAD-OFFSITE code

406

|Home Graphic Version The U.S. House of Representatives: COMMITTEE ON APPROPRIATIONS Press Releases  

E-Print Network [OSTI]

. This includes $100 million for Nuclear Waste Disposal and $350 million for Defense Nuclear Waste Disposal provided to the Office of Nuclear Energy, Science and Technology to develop an advanced spent fuel. Power Marketing Administrations The which includes the nuclear weapons program, defense nuclear

407

Options and costs for offsite disposal of oil and gas exploration and production wastes.  

SciTech Connect (OSTI)

In the United States, most of the exploration and production (E&P) wastes generated at onshore oil and gas wells are disposed of or otherwise managed at the well site. Certain types of wastes are not suitable for onsite management, and some well locations in sensitive environments cannot be used for onsite management. In these situations, operators must transport the wastes offsite for disposal. In 1997, Argonne National Laboratory (Argonne) prepared a report that identified offsite commercial disposal facilities in the United States. This information has since become outdated. Over the past year, Argonne has updated the study through contacts with state oil and gas agencies and commercial disposal companies. The new report, including an extensive database for more than 200 disposal facilities, provides an excellent reference for information about commercial disposal operations. This paper describes Argonne's report. The national study provides summaries of the types of offsite commercial disposal facilities found in each state. Data are presented by waste type and by disposal method. The categories of E&P wastes in the database include: contaminated soils, naturally occurring radioactive material (NORM), oil-based muds and cuttings, produced water, tank bottoms, and water-based muds and cuttings. The different waste management or disposal methods in the database involve: bioremediation, burial, salt cavern, discharge, evaporation, injection, land application, recycling, thermal treatment, and treatment. The database includes disposal costs for each facility. In the United States, most of the 18 billion barrels (bbl) of produced water, 149 million bbl of drilling wastes, and 21 million bbl of associated wastes generated at onshore oil and gas wells are disposed of or otherwise managed at the well site. However, under certain conditions, operators will seek offsite management options for these E&P wastes. Commercial disposal facilities are offsite businesses that accept and manage E&P wastes for a fee. Their services include waste management and disposal, transportation, cleaning of vehicles and tanks, disposal of wash water, and, in some cases, laboratory analysis. Commercial disposal facilities offer a suite of waste management methods and technologies.

Puder, M. G.; Veil, J. A.; Environmental Science Division

2007-01-01T23:59:59.000Z

408

Disposal of chemical agents and munitions stored at Anniston Army Depot, Anniston, Alabama  

SciTech Connect (OSTI)

The purpose of this Phase I report is to examined the proposed implementation of on-site disposal at Anniston Army Depot (ANAD) in light of more detailed and more recent data than those included in the Final Programmatic Environmental Impact Statement (EPEIS). Two principal issues are addressed: (1) whether or not the new data would result in identification of on-site disposal at ANAD as the environmentally preferred alternative (using the same selection method and data analysis tools as in the FPEIS), and (2) whether or not the new data indicate the presence of significant environmental resources that could be affected by on-site disposal at ANAD. In addition, a status report is presented on the maturity of the disposal technology (and now it could affect on-site disposal at ANAD). Inclusion of these more recent data into the FPEIS decision method resulted in confirmation of on-site disposal for ANAD. No unique resources with the potential to prevent or delay implementation of on-site disposal at ANAD have been identified. A review of the technology status identified four principal technology developments that have occurred since publication of the FPEIS and should be of value in the implementation of on-site disposal at ANAD: the disposal of nonlethal agent at Pine Bluff Arsenal, located near Pine Bluff, Arkansas; construction and testing of facilities for disposal of stored lethal agent at Johnston Atoll, located about 1300 km (800 miles) southwest of Hawaii in the Pacific Ocean; lethal agent disposal tests at the chemical agent pilot plant operations at Tooele Army Depot, located near Salt Lake City, Utah; and equipment advances. 18 references, 13 figs., 10 tabs.

Hunsaker, D.B. Jr.; Zimmerman, G.P.; Hillsman, E.L.; Miller, R.L.; Schoepfle, G.M.; Johnson, R.O.; Tolbert, V.R.; Kroodsma, R.L.; Rickert, L.W.; Rogers, G.O.; Staub, W.P.

1990-09-01T23:59:59.000Z

409

Licensing plan for UMTRA project disposal sites. Final [report  

SciTech Connect (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC`s acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information.

Not Available

1993-09-01T23:59:59.000Z

410

Reducing biosolids disposal costs using land application in forested areas  

SciTech Connect (OSTI)

Switching biosolids land application from a reclamation site to a forested site significantly reduced the cost of biosolids disposal at the Savannah River Site. Previous beneficial reuse programs focused on reclamation of existing borrow pits. While extremely beneficial, this program became very costly due to the regulatory requirements for groundwater monitoring, soil monitoring and frequent biosolids analyses. A new program was developed to reuse biosolids in forested areas where the biosolids could be used as a soil conditioner and fertilizer to enhance timber yield. The forested land application site was designed so that groundwater monitoring and soil monitoring could be eliminated while biosolids monitoring and site maintenance were minimized. Monitoring costs alone were reduced by 80%. Capital costs for site preparation were also significantly reduced since there was no longer a need for expensive groundwater monitoring wells.

Huffines, R.L.

1995-11-01T23:59:59.000Z

411

Risk assessment of landfill disposal sites - State of the art  

SciTech Connect (OSTI)

A risk assessment process can assist in drawing a cost-effective compromise between economic and environmental costs, thereby assuring that the philosophy of 'sustainable development' is adhered to. Nowadays risk analysis is in wide use to effectively manage environmental issues. Risk assessment is also applied to other subjects including health and safety, food, finance, ecology and epidemiology. The literature review of environmental risk assessments in general and risk assessment approaches particularly regarding landfill disposal sites undertaken by the authors, reveals that an integrated risk assessment methodology for landfill gas, leachate or degraded waste does not exist. A range of knowledge gaps is discovered in the literature reviewed to date. From the perspective of landfill leachate, this paper identifies the extent to which various risk analysis aspects are absent in the existing approaches.

Butt, Talib E. [Sustainability Centre in Glasgow (SCG), George Moore Building, 70 Cowcaddens Road, Glasgow Caledonian University, Glasgow G4 0BA, Scotland (United Kingdom)], E-mail: t_e_butt@hotmail.com; Lockley, Elaine [Be Environmental Ltd. Suite 213, Lomeshaye Business Village, Turner Road, Nelson, Lancashire, BB9 7DR, England (United Kingdom); Oduyemi, Kehinde O.K. [Built and Natural Environment, Baxter Building, University of Abertay Dundee, Bell Street, Dundee DD1 1HG, Scotland (United Kingdom)], E-mail: k.oduyemi@abertay.ac.uk

2008-07-01T23:59:59.000Z

412

Tritiated wastewater treatment and disposal evaluation for 1994  

SciTech Connect (OSTI)

This report discusses and analyzes information and issues regarding tritium and tritium management. It was prepared in response to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-05A for the evaluation of tritiated wastewater treatment and disposal. The key elements of the report are summarized as follows: Discharge of tritiated water is regulated worldwide. Differences exist in discharge limits and in regulatory philosophy from country to country and from state to state in the United States. Tritium from manmade sources is emitted into the atmosphere and discharged into the ground or directly to the oceans and to waterways that empty into the oceans. In 1989, reported worldwide emissions of tritium from nuclear power generating plants totaled almost 1,000,000 Curies (Ci).

Not Available

1994-08-01T23:59:59.000Z

413

Long-length contaminated equipment disposal process path document  

SciTech Connect (OSTI)

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

McCormick, W.A.

1998-09-30T23:59:59.000Z

414

Disposal of radioactive waste from nuclear research facilities  

E-Print Network [OSTI]

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Maxeiner, H; Kolbe, E

2003-01-01T23:59:59.000Z

415

Fort Calhoun Station disposal of spent fuel pool racks  

SciTech Connect (OSTI)

The original plan was to have the racks pulled out of the pool, washed down and wrapped and placed in Sea/Lands to be sent to a vendor for free release and disposal. In the winter of 93 the proposed quotations on the Spent Fuel Rerack Processing were all rejected. With the rerack job starting in March of 94 and the closing of Barnwell in July we were faced with what to do with the racks. Processing of the existing racks were required since if the racks were sent to Barnwell for burial intact the cost would be prohibitive, that is, if Barnwell would have stayed open. If the racks were sent to a smelter, such as Scientific Ecology Group (SEG), there are restrictions on the length of the components that can go through the smelter. If SEG were to do the rack processing (sectioning) at their facility, the cost would also be prohibitive and they would not be in a position to receive the racks until June, 1995. Therefore, bid specifications were requested for on-site volume reduction processing of the existing spent fuel storage racks, with further ultimate disposal to be performed by SEG. The processing of the racks included piping and supports. Volume reduction (VR) was an issue in the evaluation since after this process the racks were to be shipped to SEG. If a low VR ratio option was chosen, OPPD would need a significant number of shipping containers and required more radwaste shipments versus if a high VR ratio option were chosen.

Jamieson, T.W. [Omaha Public Power District, Fort Calhoun Station, NE (United States)

1995-09-01T23:59:59.000Z

416

LABORATORY EXPERIMENTS TO SIMULATE CO2 OCEAN DISPOSAL  

SciTech Connect (OSTI)

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

Stephen M. Masutani

1999-12-31T23:59:59.000Z

417

Field study of disposed solid wastes from advanced coal processes  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells.

Not Available

1992-01-01T23:59:59.000Z

418

Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INLs contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.

Danny Anderson

2014-07-01T23:59:59.000Z

419

Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to locate previously unidentified features at CASs 03-20-07, 03-20-09, 03-20-10, 03-20-11, and 06-20-03. (4) Perform field screening. (5) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present. (6) Collect quality control samples for laboratory analyses to evaluate the performance of measurement systems and controls based on the requirements of the data quality indicators. (7) If COCs are present at the surface/near surface (< 15 feet below ground surface), collect additional step-out samples to define the extent of the contamination. (8) If COCs are present in the subsurface (i.e., base of disposal hole), collect additional samples to define the vertical extent of contamination. A conservative use restriction will be used to encompass the lateral extent of subsurface contamination. (9) Stake or flag sample locations in the field, and record coordinates through global positioning systems surveying. (10) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Laura Pastor

2006-05-01T23:59:59.000Z

420

Multiple personality, a case study  

E-Print Network [OSTI]

. An exhaustive review of the literature revealed n& previous attempts at ut ilizing videotape therapy in the T. ea n&eni of rriultiple personali ty. Hnwever, via?. toping h&, s he, n !ncreosin&3!y llsea with great success in training therapists (Musan... personolity. Ir was also based on the past successes nf audio topes used in conjur!ation w!tn psychoanaiysis and hypnosis in the treat!nant of mal tip lr personalities. Following tt!e agree!nent to instItute videorape therapy inl. ! Ihe treat!ment plan...

Musick, William Daniel Anderson

1976-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

LLaannggeerrhhaannss LLaabb PPrroottooccoollss Chemical Waste Disposal Protocol.docx pg 1 of 1  

E-Print Network [OSTI]

LLaannggeerrhhaannss LLaabb PPrroottooccoollss Chemical Waste Disposal Protocol.docx pg 1 of 1 Chemical Waste Disposal Protocol For Chemical Waste Pick-Up: 1. Log on to http://www.ncsu.edu/ehs. 2. Click waste item being submitted. 7. Fill out and affix a Hazardous Waste label, from the drawer labeled

Langerhans, Brian

422

Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas  

SciTech Connect (OSTI)

This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

B. C. Rogers; P. L. Walter (Rogers and Associates Engineering Corporation); R. D. Baird

1999-08-01T23:59:59.000Z

423

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1996-02-01T23:59:59.000Z

424

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1996-05-01T23:59:59.000Z

425

Long-term surveillance plan for the Gunnison, Colorado disposal site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1996-04-01T23:59:59.000Z

426

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-04-01T23:59:59.000Z

427

ASSESSING GHG EMISSIONS FROM SLUDGE TREATMENT AND DISPOSAL ROUTES THE METHOD BEHIND GESTABOUES TOOL  

E-Print Network [OSTI]

.pradel@irstea.fr EXECUTIVE SUMMARY In 2007, 1 100 000 tons of sewage sludge were produced in France. This figure is constantly increasing and sludges have to be eliminated. Four disposal routes are currently possible: landASSESSING GHG EMISSIONS FROM SLUDGE TREATMENT AND DISPOSAL ROUTES ­ THE METHOD BEHIND GESTABOUES

Boyer, Edmond

428

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells  

E-Print Network [OSTI]

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells Hong Zhao and T. S. Zhao* Disposable paper-cups are used for the formation of graphene sheets with Fe2+ as a catalyst. The proposed synthesis strategy not only enables graphene sheets to be produced in high yield

Zhao, Tianshou

429

Disposal of Hazardous Medical Waste Policy and Procedures Commencement Date: 27 November, 1996  

E-Print Network [OSTI]

Manipulation Advisory Committee's publication, Guidelines for the Storage, Transport and Disposal of Medical" and must comply with the Guidelines for the Storage, Transport and Disposal of Medical Waste issued of their chemical, biological or physical properties. Sharps Means objects or devices having acute rigid corners

430

wastewater_sink_disposal_guidance.docx Revision Date: 10/26/2012 Page 1 of 3  

E-Print Network [OSTI]

wastewater_sink_disposal_guidance.docx Revision Date: 10/26/2012 Page 1 of 3 LABORATORY & BUILDING limitations and prohibitions established by the local wastewater treatment authority, the Massachusetts Water for wastewater disposal purposes is strictly prohibited. Hazardous Wastes: Hazardous wastes are prohibited from

Heller, Eric

431

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-02-01T23:59:59.000Z

432

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-05-01T23:59:59.000Z

433

ACTIVATION, DECAY HEAT, AND WASTE DISPOSAL ANALYSES FOR THE ARIES-AT POWER PLANT  

E-Print Network [OSTI]

ACTIVATION, DECAY HEAT, AND WASTE DISPOSAL ANALYSES FOR THE ARIES-AT POWER PLANT D. Henderson, L, decay heat and waste disposal calculations of the ARIES-AT design are performed to evaluate the safety directly into a higher initial decay heat for these structures than for the well-protected steel

California at San Diego, University of

434

Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

Timothy Solack; Carol Mason

2012-03-01T23:59:59.000Z

435

Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility  

SciTech Connect (OSTI)

This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

BURBANK, D.A.

2000-08-31T23:59:59.000Z

436

Landscape Characterization and Representativeness Analysis for Understanding Sampling Network Coverage  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

Sampling networks rarely conform to spatial and temporal ideals, often comprised of network sampling points which are unevenly distributed and located in less than ideal locations due to access constraints, budget limitations, or political conflict. Quantifying the global, regional, and temporal representativeness of these networks by quantifying the coverage of network infrastructure highlights the capabilities and limitations of the data collected, facilitates upscaling and downscaling for modeling purposes, and improves the planning efforts for future infrastructure investment under current conditions and future modeled scenarios. The work presented here utilizes multivariate spatiotemporal clustering analysis and representativeness analysis for quantitative landscape characterization and assessment of the Fluxnet, RAINFOR, and ForestGEO networks. Results include ecoregions that highlight patterns of bioclimatic, topographic, and edaphic variables and quantitative representativeness maps of individual and combined networks.

Maddalena, Damian; Hoffman, Forrest; Kumar, Jitendra; Hargrove, William

437

Landscape Characterization and Representativeness Analysis for Understanding Sampling Network Coverage  

SciTech Connect (OSTI)

Sampling networks rarely conform to spatial and temporal ideals, often comprised of network sampling points which are unevenly distributed and located in less than ideal locations due to access constraints, budget limitations, or political conflict. Quantifying the global, regional, and temporal representativeness of these networks by quantifying the coverage of network infrastructure highlights the capabilities and limitations of the data collected, facilitates upscaling and downscaling for modeling purposes, and improves the planning efforts for future infrastructure investment under current conditions and future modeled scenarios. The work presented here utilizes multivariate spatiotemporal clustering analysis and representativeness analysis for quantitative landscape characterization and assessment of the Fluxnet, RAINFOR, and ForestGEO networks. Results include ecoregions that highlight patterns of bioclimatic, topographic, and edaphic variables and quantitative representativeness maps of individual and combined networks.

Maddalena, Damian; Hoffman, Forrest; Kumar, Jitendra; Hargrove, William

2014-08-01T23:59:59.000Z

438

Offsite commercial disposal of oil and gas exploration and production waste :availability, options, and cost.  

SciTech Connect (OSTI)

A survey conducted in 1995 by the American Petroleum Institute (API) found that the U.S. exploration and production (E&P) segment of the oil and gas industry generated more than 149 million bbl of drilling wastes, almost 18 billion bbl of produced water, and 21 million bbl of associated wastes. The results of that survey, published in 2000, suggested that 3% of drilling wastes, less than 0.5% of produced water, and 15% of associated wastes are sent to offsite commercial facilities for disposal. Argonne National Laboratory (Argonne) collected information on commercial E&P waste disposal companies in different states in 1997. While the information is nearly a decade old, the report has proved useful. In 2005, Argonne began collecting current information to update and expand the data. This report describes the new 2005-2006 database and focuses on the availability of offsite commercial disposal companies, the prevailing disposal methods, and estimated disposal costs. The data were collected in two phases. In the first phase, state oil and gas regulatory officials in 31 states were contacted to determine whether their agency maintained a list of permitted commercial disposal companies dedicated to oil. In the second stage, individual commercial disposal companies were interviewed to determine disposal methods and costs. The availability of offsite commercial disposal companies and facilities falls into three categories. The states with high oil and gas production typically have a dedicated network of offsite commercial disposal companies and facilities in place. In other states, such an infrastructure does not exist and very often, commercial disposal companies focus on produced water services. About half of the states do not have any industry-specific offsite commercial disposal infrastructure. In those states, operators take their wastes to local municipal landfills if permitted or haul the wastes to other states. This report provides state-by-state summaries of the types of offsite commercial disposal facilities that are found in each state. In later sections, data are presented by waste type and then by disposal method.

Puder, M. G.; Veil, J. A.

2006-09-05T23:59:59.000Z

439

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

SciTech Connect (OSTI)

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

David Duncan

2011-05-01T23:59:59.000Z

440

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

SciTech Connect (OSTI)

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2010-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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

Criticality safety considerations in the geologic disposal of spent nuclear fuel assemblies  

SciTech Connect (OSTI)

Features of geologic disposal which hamper the demonstration that criticality cannot occur therein include possible changes of shape and form, intrusion of water as a neutron moderator, and selective leaching of spent fuel constituents. If the criticality safety of spent fuel disposal depends on burnup, independent measurements verifying the burnup should be performed prior to disposal. The status of nondestructive analysis method which might provide such verification is discussed. Calculations were performed to assess the potential for increasing the allowed size of a spent fuel disposal canister if potential water intrusion were limited by close-packing the enclosed rods. Several factors were identified which severely limited the potential of this application. The theoretical limit of hexagonal close-packing cannot be achieved due to fuel rod bowing. It is concluded that disposal canisters should be sized on the basis of assumed optimum moderation. Several topics for additional research were identified during this limited study.

Gore, B.F.; McNair, G.W.; Heaberlin, S.W.

1980-05-01T23:59:59.000Z

442

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

SciTech Connect (OSTI)

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2011-03-01T23:59:59.000Z

443

Long-term surveillance plan for the Shiprock disposal site, Shiprock, New Mexico  

SciTech Connect (OSTI)

The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. This Shiprock, New Mexico, LTSP documents whether the land and interests are owned by the US or an Indian tribe and describes in detail the long-term care program through the UMTRA Project Office.

Not Available

1993-12-01T23:59:59.000Z

444

Grout long radius flow testing to support Saltstone disposal Unit 5 design  

SciTech Connect (OSTI)

The Saltstone Facility, located within the Savannah River Site (SRS) near Aiken, South Carolina, consists of two facility segments: The Saltstone Production Facility (SPF) and the Saltstone Disposal Facility (SDF). The SPF receives decontaminated legacy low level sodium salt waste solution that is a byproduct of prior nuclear material processing. The salt solution is mixed with cementitious materials to form a grout slurry known as Saltstone. The grout is pumped to the SDF where it is placed in a Saltstone Disposal Unit (SDU) to solidify. SDU 6 is referred to as a mega vault and is currently in the design stage. The conceptual design for SDU 6 is a single cell, cylindrical geometry approximately 114.3 meters in diameter by 13.1 meter high and is larger than previous cylindrical SDU designs, 45.7 meters in diameter by 7.01 meters high (30 million gallons versus 2.9 million gallons of capacity). Saltstone slurry will be pumped into the new waste disposal unit through roof openings at a projected flow rate of about 34.1 cubic meters per hour. Nine roof openings are included in the design to discharge material into the SDU with an estimated grout pour radius of 22.9 to 24.4 meters and initial drop height of 13.1 meters. The conceptual design for the new SDU does not include partitions to limit the pour radius of the grout slurry during placement other than introducing material from different pour points. This paper addresses two technical issues associated with the larger diameter of SDU 6; saltstone flow distance in a tank 114.3 meters in diameter and quality of the grout. A long-radius flow test scaled to match the velocity of an advancing grout front was designed to address these technology gaps. The emphasis of the test was to quantify the flow distance and to collect samples to evaluate cured properties including compressive strength, porosity, density, and saturated hydraulic conductivity. Two clean cap surrogate mixes (saltstone premix plus water) were designed to simulate slurry with the reference saltstone rheology and a saltstone with extra water from the process flushing operation. Long-radius flow tests were run using approximately 4.6 cubic meters of each of these mixes. In both tests the pump rate was 0.063 liters/second (1 gpm). A higher pump rate, 0.19 liters/second (3 gpm), was used in a third long-radius flow test. The angle of repose of the grout wedges increased as a function of time in all three tests. The final angles of repose were measured at 3.0, 2.4, and 0.72. The pump rate had the largest effect on the radial flow distance and slope of the grout surface. The slope on the pour placed at 0.19 liters/second (3 gpm) was most representative of the slope on the grout currently being pumped into SDU 2 which is estimated to be 0.7 to 0.9. The final grout heights at 1/3 of a meter from the discharge point were 115, 105, and 38 cm. Entrapped air (? 0.25 cm bubbles) was also observed in all of the mixes. The entrapped air appeared to be released from the flows within about 3.1 meters (10 feet) of the discharge point. The bleed water was clear but had a thin layer of floating particulates. The bleed water should be retrievable by a drain water collection system in SDU 6 assuming the system does not get clogged. Layering was observed and was attributed to intervals when the hopper was being cleaned. Heat from the hydration reactions was noticeable to the touch.

Stefanko, D. B.; Langton, C. A.; Serrato, M. G.; Brooks, T. E. II; Huff, T. H.

2013-02-24T23:59:59.000Z

445

Grout Long Radius Flow Testing to Support Saltstone Disposal Unit 6 Design - 13352  

SciTech Connect (OSTI)

The Saltstone Facility, located within the Savannah River Site (SRS) near Aiken, South Carolina, consists of two facility segments: The Saltstone Production Facility (SPF) and the Saltstone Disposal Facility (SDF). The SPF receives decontaminated legacy low level sodium salt waste solution that is a byproduct of prior nuclear material processing. The salt solution is mixed with cementitious materials to form a grout slurry known as 'Saltstone'. The grout is pumped to the SDF where it is placed in a Saltstone Disposal Unit (SDU) to solidify. SDU 6 is referred to as a 'mega vault' and is currently in the design stage. The conceptual design for SDU 6 is a single cell, cylindrical geometry approximately 114.3 meters in diameter by 13.1 meter high and is larger than previous cylindrical SDU designs, 45.7 meters in diameter by 7.01 meters high (30 million gallons versus 2.9 million gallons of capacity). Saltstone slurry will be pumped into the new waste disposal unit through roof openings at a projected flow rate of about 34.1 cubic meters per hour. Nine roof openings are included in the design to discharge material into the SDU with an estimated grout pour radius of 22.9 to 24.4 meters and initial drop height of 13.1 meters. The conceptual design for the new SDU does not include partitions to limit the pour radius of the grout slurry during placement other than introducing material from different pour points. This paper addresses two technical issues associated with the larger diameter of SDU 6; Saltstone flow distance in a tank 114.3 meters in diameter and quality of the grout. A long-radius flow test scaled to match the velocity of an advancing grout front was designed to address these technology gaps. The emphasis of the test was to quantify the flow distance and to collect samples to evaluate cured properties including compressive strength, porosity, density, and saturated hydraulic conductivity. Two clean cap surrogate mixes (Saltstone premix plus water) were designed to simulate slurry with the reference Saltstone rheology and a Saltstone with extra water from the process flushing operation. Long-radius flow tests were run using approximately 4.6 cubic meters of each of these mixes. In both tests the pump rate was 0.063 liters/second (1 gpm). A higher pump rate, 0.19 liters/second (3 gpm), was used in a third long-radius flow test. The angle of repose of the grout wedges increased as a function of time in all three tests. The final angles of repose were measured at 3.0 deg., 2.4 deg., and 0.72 deg.. The pump rate had the largest effect on the radial flow distance and slope of the grout surface. The slope on the pour placed at 0.19 liters/second (3 gpm) was most representative of the slope on the grout currently being pumped into SDU 2 which is estimated to be 0.7 deg. to 0.9 deg. The final grout heights at 1/3 of a meter from the discharge point were 115, 105, and 38 cm. Entrapped air (? 0.25 cm bubbles) was also observed in all of the mixes. The entrapped air appeared to be released from the flows within about 3.1 meters (10 feet) of the discharge point. The bleed water was clear but had a thin layer of floating particulates. The bleed water should be retrievable by a drain water collection system in SDU 6 assuming the system does not get clogged. Layering was observed and was attributed to intervals when the hopper was being cleaned. Heat from the hydration reactions was noticeable to the touch. (authors)

Stefanko, D.B.; Langton, C.A.; Serrato, M.G. [Savannah River National Laboratory, Savannah River Nuclear Solutions, LLC, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Nuclear Solutions, LLC, Savannah River Site, Aiken, SC 29808 (United States); Brooks, T.E. II; Huff, T.H. [Savannah River Remediation, LLC, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River Remediation, LLC, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

446

Justification Of The Use Of Boreholes For Disposal Of Sealed Radiological Sources  

SciTech Connect (OSTI)

Soon there will be only 14 states in two compacts that are able to dispose of Low Level Waste (LLW): the Northwest and Rocky Mountain compact with disposal options in Richland, Washington, and the Atlantic compact with disposal options in Barnwell, South Carolina. How do states not in one of the two compacts dispose of their LLW? The Off-Site Source Recovery Project can take possession and dispose of some of the unwanted transuranic sources at the Waste Isolation Pilot Plant (WIPP). However, there will be no path forward for states outside of the two compacts for disposal of their non-transuranic LLW. A solution that has been much discussed, debated and researched, but has not been put into wide scale practice, is the borehole disposal concept. It is the author's position that companies that drill and explore for oil have been disposing of sources in borehole-like structures for years. It should be noted that these companies are not purposely disposing of these sources, but the sources are irretrievable and must be abandoned. Additionally, there are Nuclear Regulatory Commission (NRC) regulations that must be followed to seal the well that contains the lost and abandoned source. According to the NRC Event Notification Reports database, there were a minimum of 29 reports of lost and abandoned sources in oil wells between December 1999 and October 2006. The sources were lost at depths between 2,018-18,887 feet, or 600-5,750 meters. The companies that are performing explorations with the aid of sealed radiological sources must follow regulation 10 CFR Part 39. Subsection 15 outlines the procedures that must be followed if sources are determined to be irretrievable and abandoned in place. If the NRC allows and has regulations in place for oil companies, why can't states and/or companies be allowed to dispose of LLW in a similar fashion?

Zarling, John [Los Alamos National Laboratory; Johnson, Peter [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

447

Wave Energy Resources Representative Sites Around the Hawaiian Islands  

E-Print Network [OSTI]

Wave Energy Resources for Representative Sites Around the Hawaiian Islands Prepared by: Luis A. Vega Ph.D October 11, 2010 #12;Wave Power Resources off the Hawaiian Islands October 11, 2010 1 Foreword This report provides wave energy resource information required to select coastal segments

448

DATE: December 11, 2013 MEMO TO: Curricular Representative  

E-Print Network [OSTI]

Instruction Modes List: This report lists sections with an Instruction Mode not set to `P' in ISIS. · Meets Attendance List: This report lists sections coded in ISIS as optional. · Curricular Representative List can be run in ISIS, and displays real-time curricular data for auditing. In ISIS: Reporting Tools

Wisconsin at Madison, University of

449

Antibiotics and access to clean water represent two major  

E-Print Network [OSTI]

ABSTRACT Antibiotics and access to clean water represent two major advances for public health of clean, potable water to homes and businesses, while eliminating resulting sewage. However, today, our in spreading re- sistance. At the same time, due to growing pressure on our water resources, we are forging new

Subramanian, Venkat

450

Representing and encoding plant architecture: A review Christophe Godin*  

E-Print Network [OSTI]

Review Representing and encoding plant architecture: A review Christophe Godin* CIRAD, Programme de and topological organisation of these components defines the plant architecture. Before the early 1970's-performance computers have become available for plant growth analysis and simulation, trig- gering the development

Paris-Sud XI, Université de

451

A Mathematical Programming Model for Scheduling Pharmaceutical Sales Representatives  

E-Print Network [OSTI]

% to nearly 80,000 from 50,000, and that visits by sales representatives to doctors' offices increased ten. In the next section, we present some background material relevant to this research. Then, in Section 3, we instances in Section 4. We present concluding remarks in Section 5. 2. Background For multi

Gautam, Natarajan

452

66 Academic Nurse Program representatives assist the School  

E-Print Network [OSTI]

interviews, professional development, and dealing with the unknown. Anesthesia Program Representative: Laura of safe surgery and anesthesia practices. Since gradua- tion, he has been involved in global anesthesia also currently serves on the Anesthesia Committee for the Global Alliance for Surgical and Anesthesia

Grishok, Alla

453

Does convective aggregation need to be represented in cumulus parameterizations?  

E-Print Network [OSTI]

Does convective aggregation need to be represented in cumulus parameterizations? Isabelle Tobin,1 in phenomena such as ``hot spots'' or the Madden-Julian Oscillation. These findings support the need climate models lack any such representation. The ability of a cloud system- resolving model to reproduce

454

Representing Topological Relationships between Complex Regions by F-Histograms  

E-Print Network [OSTI]

Representing Topological Relationships between Complex Regions by F-Histograms Lukasz Wawrzyniak between two regions in terms of the thirteen Allen relations. An index to measure the complexity Work in the modeling of topological relationships often relies on an extension into the spatial domain

Matsakis, Pascal

455

Appointment of Contracting Officers and Contracting Officer's Representatives  

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

To establish procedures governing the selection, appointment, and termination of contracting officers and for the appointment of contracting officer's representatives. To ensure that only trained and qualified procurement and financial assistance professionals, within the scope of this Order, serve as contracting officers. Cancels DOE O 541.1. Canceled by DOE O 541.1B.

2000-10-27T23:59:59.000Z

456

Anthropogenic Biomes ver. 1 Anthropogenic biomes represent heterogeneous  

E-Print Network [OSTI]

defined by population density and vegetation cover. The 21 biomes are grouped into six major categoriesAnthropogenic Biomes ver. 1 Africa Anthropogenic biomes represent heterogeneous landscape mosaics: Populated irrigated cropland 34: Populated rainfed cropland 35: Remote croplands 41: Residential rangelands

Columbia University

457

US House of Representatives Appropriation Committee Report May 18, 2005  

E-Print Network [OSTI]

US House of Representatives Appropriation Committee Report May 18, 2005 Fusion Energy Sciences The Committee recommendation for fusion energy sciences is $295,155,000, an increase of $5,605,000 over that two-thirds of the proposed increase for the International Thermonuclear Experimental Reactor (ITER

458

Representing Abductive Practical Reasoning as an Action-Based  

E-Print Network [OSTI]

Representing Abductive Practical Reasoning as an Action-Based Alternating Transition System Floris present an approach to abductive reasoning by examin- ing it in the context of an argumentation scheme to rea- son abductively about how an agent might have acted to find itself in a particular sceanrio

Atkinson, Katie

459

INTRODUCTION The mammalian hair follicle is a representative but highly  

E-Print Network [OSTI]

INTRODUCTION The mammalian hair follicle is a representative but highly complex epithelial organ, hair follicle induction requires complex signaling between the two apposing tissue layers, which to the formation of the hair follicle, which contain the dermal papilla, proliferating matrix cells and slowly

Chuong, Cheng-Ming

460

Numerical simulation of hydrothermal salt separation process and analysis and cost estimating of shipboard liquid waste disposal  

E-Print Network [OSTI]

Due to environmental regulations, waste water disposal for US Navy ships has become a requirement which impacts both operations and the US Navy's budget. In 2006, the cost for waste water disposal Navy-wide was 54 million ...

Hunt, Andrew Robert

2007-01-01T23:59:59.000Z

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


461

Disposal of NORM-contaminated oil field wastes in salt caverns -- Legality, technical feasibility, economics, and risk  

SciTech Connect (OSTI)

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

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

1998-07-01T23:59:59.000Z

462

Bodleian Libraries'Admissions Office Personal Details  

E-Print Network [OSTI]

and held securely in the University's shared Development and Alumni Relations System (DARS): DARS provides.alumni.ox.ac.uk/data_protection for information on the way in which your personal data are held and used in DARS. Some sensitive personal data may be held in DARS. If, at any time, you have any queries about the use of your personal data in DARS or wish

Oxford, University of

463

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

NSTec Environmental Restoration

2009-07-31T23:59:59.000Z

464

Department of Energy Personal Property Management Program  

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

The order sets forth requirements for personal property management and accountability. Admin Chg 1, dated 10-22-12, cancels DOE O 580.1A.

2012-03-30T23:59:59.000Z

465

ORIGINAL CONTRIBUTION Multidrug Resistance Among Persons  

E-Print Network [OSTI]

ORIGINAL CONTRIBUTION Multidrug Resistance Among Persons With Tuberculosis in California, 1994- tinuestohaveasubstantialpublichealth impact, leading in 2003 to 233 deaths and more than 132 cases diagnosed among children younger

Marathe, Achla

466

Type B Accident Investigation, Subcontractor Employee Personal...  

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

ignited the right leg of his 100% cotton anticontamination (anti-c) coveralls and the plastic bootie. Type B Accident Investigation, Subcontractor Employee Personal Protective...

467

Personal Property Disposition - Community Reuse Organizations...  

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

Owen (signed) Director, Office of Worker and Community Transition Department of Energy Washington, DC 20505 January 22, 2003 Disposition of Excess Personal Property...

468

National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

Peggy Hinman

2010-10-01T23:59:59.000Z

469

Preliminary technical and legal evaluation of disposing of nonhazardous oil field waste into salt caverns  

SciTech Connect (OSTI)

Caverns can be readily formed in salt formations through solution mining. The caverns may be formed incidentally, as a result of salt recovery, or intentionally to create an underground chamber that can be used for storing hydrocarbon products or compressed air or disposing of wastes. The purpose of this report is to evaluate the feasibility, suitability, and legality of disposing of nonhazardous oil and gas exploration, development, and production wastes (hereafter referred to as oil field wastes, unless otherwise noted) in salt caverns. Chapter 2 provides background information on: types and locations of US subsurface salt deposits; basic solution mining techniques used to create caverns; and ways in which salt caverns are used. Later chapters provide discussion of: federal and state regulatory requirements concerning disposal of oil field waste, including which wastes are considered eligible for cavern disposal; waste streams that are considered to be oil field waste; and an evaluation of technical issues concerning the suitability of using salt caverns for disposing of oil field waste. Separate chapters present: types of oil field wastes suitable for cavern disposal; cavern design and location; disposal operations; and closure and remediation. This report does not suggest specific numerical limits for such factors or variables as distance to neighboring activities, depths for casings, pressure testing, or size and shape of cavern. The intent is to raise issues and general approaches that will contribute to the growing body of information on this subject.

Veil, J.; Elcock, D.; Raivel, M.; Caudle, D.; Ayers, R.C. Jr.; Grunewald, B.

1996-06-01T23:59:59.000Z

470

Long-term surveillance plan for the Maybell, Colorado Disposal Site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-12-01T23:59:59.000Z

471

Long-term surveillance plan for the Gunnison, Colorado disposal site. Revision 2  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the US Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance.

NONE

1997-02-01T23:59:59.000Z

472

Long-term surveillance plan for the South Clive Disposal Site, Clive, Utah  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the US Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project South Clive disposal site in Clive, Utah. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CRF Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the South Clive disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the South Clive site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the South Clive disposal site performs as designed. The program`s primary activity is site inspections to identify threats to disposal cell integrity.

NONE

1996-03-01T23:59:59.000Z

473

Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney disposal site. The site is in Mesa County near Grand Junction, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-04-01T23:59:59.000Z

474

Long-term surveillance plan for the Maybell, Colorado Disposal Site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-09-01T23:59:59.000Z

475

Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project  

SciTech Connect (OSTI)

Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

NSTec Environmental Management

2009-01-31T23:59:59.000Z

476

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01T23:59:59.000Z

477

Using performance assessment for radioactive waste disposal decision making -- implementation of the methodology into the third performance assessment iteration of the Greater Confinement Disposal site  

SciTech Connect (OSTI)

The US Department of Energy is responsible for the disposal of a variety of radioactive wastes. Some of these wastes are prohibited from shallow land burial and also do not meet the waste acceptance criteria for proposed waste repositories at the Waste Isolation Pilot Plant (WIPP) and Yucca Mountain. These have been termed ``special-case`` waste and require an alternative disposal method. From 1984 to 1989, the Department of Energy disposed of a small quantity of special-case transuranic wastes at the Greater Confinement Disposal (GCD) site at the Nevada Test Site. In this paper, an iterative performance assessment is demonstrated as a useful decision making tool in the overall compliance assessment process for waste disposal. The GCD site has been used as the real-site implementation and test of the performance assessment approach. Through the first two performance assessment iterations for the GCD site, and the transition into the third, we demonstrate how the performance assessment methodology uses probabilistic risk concepts to guide affective decisions about site characterization activities and how it can be used as a powerful tool in bringing compliance decisions to closure.

Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States); Baer, T.A. [GRAM, Inc., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

478

Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site  

SciTech Connect (OSTI)

This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd{sup 3} (4,580 m{sup 3}) of glass gems prior to disposal. This report documents Sandia National Laboratories` preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment.

Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Price, L.L. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Beta Inc. (United States)

1997-09-01T23:59:59.000Z

479

Operating limit evaluation for disposal of uranium enrichment plant wastes  

SciTech Connect (OSTI)

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

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

1996-02-01T23:59:59.000Z

480

Stabilization of a mixed waste sludge for land disposal  

SciTech Connect (OSTI)

A solidification and stabilization technique was developed for a chemically complex mixed waste sludge containing nitrate processing wastes, sewage sludge and electroplating wastewaters, among other wastes. The sludge is originally from a solar evaporation pond and has high concentrations of nitrate salts; cadmium, chromium, and nickel concentrations of concern; and low levels of organic constituents and alpha and beta emitters. Sulfide reduction of nitrate and precipitation of metallic species, followed by evaporation to dryness and solidification of the dry sludge in recycled high density polyethylene with added lime was determined to be a satisfactory preparation for land disposal in a mixed waste repository. The application of post-consumer polyethylene has the added benefit of utilizing another problem-causing waste product. A modified Toxicity Characteristic Leaching Procedure was used to determine required treatment chemical dosages and treatment effectiveness. The waste complexity prohibited use of standard chemical equilibrium methods for prediction of reaction products during treatment. Waste characterization followed by determination of thermodynamic feasibility of oxidation and reduction products. These calculations were shown to be accurate in laboratory testing. 13 refs., 3 figs., 2 tabs.

Powers, S.E.; Zander, A.K. [Clarkson Univ., Potsdam, NY (United States)

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "representing disposable personal" 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.


481

Unreviewed Disposal Question Evaluation: Backfill Soil Compaction Requirements  

SciTech Connect (OSTI)

One intent of DOE Order 435.1 (USDOE 1999a ), as expressed in the performance assessment/composite analysis guidance (USDOE 1999c), is to ensure that proposed changes in wasteforms, containers, radionuclide inventories, facility design, and operations are reviewed to ensure that the assumptions, results, and conclusions of the DOE approved performance assessment (PA) (WSRC 2000), and composite analysis (CA) (WSRC 1997), as well as any Special analyses (SA) that might have been performed, remain valid (i.e., that the proposed change is bounded by the PA and CA) and the changes are within the bounds of the Disposal Authorization Statement (USDOE 1999b). The goal is to provide flexibility in day-to-day operation and to require those issues with a significant impact on the PA's conclusions, and therefore the projected compliance with performance objectives/measures, to be identified and brought to the proper level of attention. It should be noted that the term performance measure is used t o describe site specific adaptations of the DOE Order 435.1 Performance Objectives and requirements (e.g., performance measures such as applying drinking water standards to the groundwater impacts assessment). The intent of this document is to provide an evaluation of the issues identified within Problem Identification Report (PIR) number 2002-PIR-26-0050 (Kukraja 2002).

Phifer, M.A.

2003-04-15T23:59:59.000Z

482