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Note: This page contains sample records for the topic "rates disposable income" 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

Lifeline electric rates and alternative approaches to the problems of low-income ratepayers. Ten case studies of implemented programs  

SciTech Connect (OSTI)

Program summaries, issue developments, governmental processes, and impacts are discussed for 10 case studies dealing with lifeline electric rates and alternative approaches to the problems of low-income ratepayers, namely; the Boston Edison rate freeze; the California lifeline; Florida Power and Light conservation rate; the Iowa-Illinois Gas and Electric small-use rate; the Maine demonstration lifeline program; the Massachusetts Electric Company A-65 rate; the Michigan optional senior citizen rate; the Narragansett Electric Company A-65 SSI rate; the Northern States Power Company conservation rate break; and the Potomac Electric Power Company rate freeze. (MCW)

Not Available

1980-07-01T23:59:59.000Z

2

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

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

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.

6

Farm Income Taxation  

E-Print Network [OSTI]

Income tax planning and management involves being aware of tax alternatives and knowing how to integrate them with other management data to accomplish the taxpayer's objectives. This publication discusses various alternatives for tax planning....

McEowen, Roger A.

1999-06-23T23:59:59.000Z

7

Some Fundamental Experiments on Apparent Dissolution Rate of Gas Phase in the Groundwater Recovery Processes of the Geological Disposal System - 12146  

SciTech Connect (OSTI)

The apparent dissolution rates of gas phase in the co-presence of solid phase were examined by in-room experiments in this study. The apparent dissolution rate of gas phase q (mol/m{sup 3}.s) was generally defined by q=aK{sub L}(?P{sub g}-c), where a (1/m) is specific surface area of the interface between gas and liquid phases, K{sub L} (m/s) is overall mass transfer coefficient, ? (mol/(Pa.m{sup 3})) is reciprocal number of Henry constant, P{sub g} (Pa) is partial pressure of gas phase, and c (mol/m{sup 3}) is the concentration of gas component in liquid phase. As a model gas, CO{sub 2} gas was used. For evaluating the values of K{sub L}, this study monitored pH or the migration rate of the interface between water/gas phases, using some experiments such as the packed beds and the micro channel consisting of granite chip and rubber sheet including a slit. In the results, the values of K{sub L} were distributed in the range from 5.0x10{sup -6} m/s to 5.0x10{sup -7} m/s. These values were small, in comparison with that (7.8x10{sup -4} m/s) obtained from the bubbling test where gas phase was continually injected into deionized water without solid phase. This means that the solid phase limits the local mixing of water phase near gas-liquid interfaces. (authors)

Yoshii, Taiki; Niibori, Yuichi; Mimura, Hitoshi [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, 6-6-01-2, Aramaki, Aza-Aoba, Aoba-ku, Sendai 980-8579 (Japan)

2012-07-01T23:59:59.000Z

8

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

9

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.

10

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.

11

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

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

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

14

Current trends in income statements  

E-Print Network [OSTI]

determined, Actually& there seems to be little qzesC on as to the most desiz able method of designating tire remainder that represents the nst income~. 9ssignations stzch as "nst income "~ "nst profit"~ "net income for the pear", and "net profit...

Cass, Edwin Childers

1948-01-01T23:59:59.000Z

15

Exceptional income from sale  

E-Print Network [OSTI]

Pocket Guide 2005-06 Imperial College Income by Source 1997-2005 These statistics are the latest-00 2000-01 2001-02 2002-03 2003-04 2004-05 2005-06 2005-06 2004-05 % change over Nos. % total Nos. % total 100.0 -10.7 -14.2 Part-Time Student Numbers 2005-06 2004-05 % change over Nos. total Nos. total 1 year

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 "rates disposable income" 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

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.

34

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

35

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

36

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.

37

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.

38

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.

39

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.

40

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.

Note: This page contains sample records for the topic "rates disposable income" 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

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

42

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

43

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

44

Low-Income Weatherization: The Human Dimension  

Broader source: Energy.gov [DOE]

This presentation focuses on how the human dimension saves energy within low-income weatherization programs.

45

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

46

Income Protection (IP) Insurance  

E-Print Network [OSTI]

of the daily futures market closing prices for the insured crop prior to the sales closing date and during harvest. IP uses the Group Risk Plan?s (GRP) county yield index to adjust IP premium rates. The insurance is provided for an enter- prise unit... equals 27.5 percent of the approved yield times 100 percent of the projected price. An insured?s total guaranteed dollar amount of protection is the net acres of the insured crop (acres times share) in the county multiplied by the IP dollar guaran- tee...

Stokes, Kenneth; Barnaby, G. A. Art; Waller, Mark L.; Outlaw, Joe

1999-06-09T23:59:59.000Z

47

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

48

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

49

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

50

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

51

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

52

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...

53

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...

54

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...

55

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...

56

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

57

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...

58

Incomes of Migratory Agricultural Workers.  

E-Print Network [OSTI]

.64 Colorado 5.35 Minnesota Wisconsin Washington Ohio California Arizona Idaho Illinois North Dakota Other states1 Includes some work in Mexico. !ndicative of family income than are data on in- jividual workers. Average earnings of the fam- dies..., BY STATES, MIGRATORY FARMWORKERS, SOUTH TEXAS, 1956 State and Average Average type of work days earnings worked per worker per per day North Dakota Sugar beets Potatoes Ohio Sugar beets Potatoes Tomatoes Other crops Oklahoma Cotton Oregon...

Sargent, Frederic O.; Metzler, William H.

1960-01-01T23:59:59.000Z

59

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

60

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

62

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

63

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

64

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

Gasoline and Diesel Fuel Update (EIA)

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) " ,"ClickPipelines About U.S.30Natural Gas Glossary529 633 6221,2372003ofDec. 31 705PC'sFigure

65

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

66

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

67

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

68

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...

69

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...

70

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...

71

SAMPLE PATENT INCOME DISTRIBUTIONS (as % of Net Income available for distribution)  

E-Print Network [OSTI]

SAMPLE PATENT INCOME DISTRIBUTIONS (as % of Net Income available for distribution) (Old Policy Outstanding Legal Costs % OF NET INCOME AVAILABLE FOR DISTRIBUTIONS PATENTS OLD POLICY CURRENT POLICY Inventor (Patent) Share 42.5% * 35% Research Share to LAB 4.6% 9.0% Research Share to Department or Home Academic

Fainman, Yeshaiahu

72

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

73

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

74

Income and Poverty in a Developing Economy  

E-Print Network [OSTI]

We present a stochastic agent-based model for the distribution of personal incomes in a developing economy. We start with the assumption that incomes are determined both by individual labour and by stochastic effects of trading and investment. The income from personal effort alone is distributed about a mean, while the income from trade, which may be positive or negative, is proportional to the trader's income. These assumptions lead to a Langevin model with multiplicative noise, from which we derive a Fokker-Planck (FP) equation for the income probability density function (IPDF) and its variation in time. We find that high earners have a power-law income distribution while the low income groups have a Levy IPDF. Comparing our analysis with the Indian survey data (obtained from the world bank website) taken over many years we obtain a near-perfect data collapse onto our model's equilibrium IPDF. The theory quantifies the economic notion of ``given other things''. Using survey data to relate the IPDF to actual...

Chattopadhyay, Amit K; Mallick, Sushanta K

2009-01-01T23:59:59.000Z

75

Fixed Income Division Nomura International plc  

E-Print Network [OSTI]

Fixed Income Division © Nomura International plc Symmetry methods for quadratic Gaussian models International plc Outline Motivation The quadratic Gaussian distribution The quadratic Gaussian process The quadratic Gaussian model #12;Fixed Income Division 3© Nomura International plc Part 1 Motivation #12;Fixed

Macrina, Andrea

76

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

77

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

78

Measurement and Verification of Low Income Energy Efficiency...  

Open Energy Info (EERE)

Low Income Energy Efficiency Programs in Brazil: Methodological Challenges Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Measurement and Verification of Low Income...

79

Proposed Structure and Organizing Principles for Low Income Energy...  

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

Structure and Organizing Principles for Low Income Energy Efficiency Workgroup 1 Background As part of Post-2011-Review, BPA agreed to convene a low income energy efficiency...

80

Better Buildings Program San Jose - Serving Moderate Income Residents...  

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

Program San Jose - Serving Moderate Income Residents Better Buildings Program San Jose - Serving Moderate Income Residents Provides an overview of the program components and goals,...

Note: This page contains sample records for the topic "rates disposable income" 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

Income Tax Deduction for Energy Efficiency Upgrades  

Broader source: Energy.gov [DOE]

Idaho residents with homes built or under construction before 2002, or who had a building permit issued before January 1, 2002, qualify for an income tax deduction for 100% of the cost of...

82

Residential Renewable Energy Income Tax Credit  

Broader source: Energy.gov [DOE]

Massachusetts allows a 15% credit -- up to $1,000 -- against the state income tax for the net expenditure* of a renewable-energy system (including installation costs) installed on an individuals...

83

University of Toronto Income Tax Guide  

E-Print Network [OSTI]

of Services 4.1 Teaching 4.1.1 Degree programs 4.1.2 Diploma and certificate programs 4.1.3 Continuing education 4.1.4 Short courses, seminars 4.1.5 Guest lecturers 4.2 Research 4.2.1 Research grants 4.2.2 Self of this income tax guide is to assist departments to determine the correct classification for income tax purposes

Sun, Yu

84

Income Statement -- A Financial Management Tool  

E-Print Network [OSTI]

(Accounts Receivable) Farm Cash Operating Expenses ? Change in Inventory Value of Accrued ? Expense, Production Supply Expense, and Accrued Interest Expense Depreciation Expenses ? Gain or Loss on Sale of Farm Capital Assets ? Gain or Loss Due... on Sale of Breeding ? Livestock Farm Business Receipts The principal source of farm income is the sale of livestock, grain and other farm products. Other income is from agricultural program pay- ments, custom work and dividends. Changes in Inventory...

Klinefelter, Danny A.

2008-09-16T23:59:59.000Z

85

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

86

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

87

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,...

88

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...

89

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

90

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

91

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.

92

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

93

Incomes of Rural Families in Northeast Texas.  

E-Print Network [OSTI]

Summary i This study deals on a sample basis with the income levels, income sources and farm and human re- source characteristics of the 88,000 rural open-country families in a 24-county area of Northeast Texas. ) Low levels of living... mainly from small-scale crop to s~all- scale livestock farming. In 1955, 49,000 of the area's rural families were farm families and 39,000 were nonfarm families, or 55 percent and 45 percent, respectively. However, 21 percent of all farmers were full...

Southern, John H.; Hendrix, W. E.

1959-01-01T23:59:59.000Z

94

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

95

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

96

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

97

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

98

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:...

99

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...

100

Unrelated Business Income Tax (UBIT) Policy  

E-Print Network [OSTI]

AND PURPOSE The purpose of this policy is to ensure that the Colorado School of Mines ("Mines") complies educational mission: instruction; research; and public service in energy, mineral engineering, and mineral subject it to income taxation by the state and federal government. Recent IRS audits of institutions

Note: This page contains sample records for the topic "rates disposable income" 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

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

102

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

103

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.

104

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.

105

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

106

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

107

Regional economic impacts of changes in electricity rates resulting from Western Area Power Administration`s power marketing alternatives  

SciTech Connect (OSTI)

This technical memorandum describes an analysis of regional economic impacts resulting from changes in retail electricity rates due to six power marketing programs proposed by Western Area Power Administration (Western). Regional economic impacts of changes in rates are estimated in terms of five key regional economic variables: population, gross regional product, disposable income, employment, and household income. The REMI (Regional Impact Models, Inc.) and IMPLAN (Impact Analysis for Planning) models simulate economic impacts in nine subregions in the area in which Western power is sold for the years 1993, 2000, and 2008. Estimates show that impacts on aggregate economic activity in any of the subregions or years would be minimal for three reasons. First, the utilities that buy power from Western sell only a relatively small proportion of the total electricity sold in any of the subregions. Second, reliance of Western customers on Western power is fairly low in each subregion. Finally, electricity is not a significant input cost for any industry or for households in any subregion.

Allison, T.; Griffes, P.; Edwards, B.K.

1995-03-01T23:59:59.000Z

108

The Farmer's Conundrum: Income from Biofuels or Protect the Soil...  

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

The Farmer's Conundrum: Income from Biofuels or Protect the Soil? The Farmer's Conundrum: Income from Biofuels or Protect the Soil? July 1, 2010 - 11:39am Addthis Lindsay Gsell...

109

Dairy Price and Income Support Policy.  

E-Print Network [OSTI]

TDoe Z TA245.7 8873 NO.1588 B-1588 Texas Agricultural Extension Service ~ ~ ________________________________ aD ________ __ ~ A~PC LIB R A R Y AGRICULTURAL' FOOD POLICY CENTER SEP 2 7 1988 x s A&M Universit DAIRY PRICE AND INCOME SUPPORT... POLICY Texas Agricultural Extension Service. Zerle L. Carpenter, Director. The Texas A&M University System. College Station, Texas Contents 1. Policy Perspectives, Problems, Goals and Tools .................... 1 2. Cost Pricing...

Schwart, Robert B. Jr; Knutson, Ronald D.; Cropp, Robert; Harris, Harold M.; Jacobson, Robert E.; Novakovic, Andrew

1988-01-01T23:59:59.000Z

110

Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah  

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 Mexican Hat, Utah, disposal site. 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 Mexican Hat disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the disposal site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Mexican Hat disposal site performs as designed. The program is based on two distinct types of activities: (1) site inspections to identify potential threats to disposal cell integrity, and (2) monitoring of selected seeps to observe changes in flow rates and water quality. 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. 18 refs., 6 figs., 1 tab.

NONE

1997-05-01T23:59:59.000Z

111

Evaluating Equality using Parametric Income Distribution Models An exploration of alternative effects using a Dagum Parametric Income Distribution Model  

E-Print Network [OSTI]

to the study of income policy effects on the distribution of personal income. A parametric model of the Dagum on income data from several countries: Canada, the United States, Italy and Argentina. Therefore, the model and increased unemployment in most of the developed as well as developing countries. For policy- makers

Ortega, Esther Ruiz

112

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

113

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

114

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

115

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

116

Progress Report Workgroup #3 Low Income  

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 MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16Hamada winsProgress Report Workgroup #3 Low Income

117

Progress Report Workgroup #3: Low Income  

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 MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16Hamada winsProgress Report Workgroup #3 Low Income

118

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

119

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

120

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

122

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

123

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

124

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

125

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

126

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...

127

Better Buildings Residential Network Multi-Family & Low-Income...  

Energy Savers [EERE]

of choice, by providing information and options * Provide loan programs that fill market gaps * Offer resources * Make connections * Serve low- and moderate-income families...

128

Approaches to Electric Utility Energy Efficiency for Low Income...  

Open Energy Info (EERE)

Electric Utility Energy Efficiency for Low Income Customers in a Changing Regulatory Environment Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Approaches to Electric...

129

Effective Energy Behavior Change for Low-Income Weatherization Clients  

Broader source: Energy.gov [DOE]

This document contains the transcript for the Effective Energy Behavior Change for Low-Income Weatherization Clients webinar presented on May 31, 2012.

130

Price, costs and income trends for New Zealand pastoral farms.  

E-Print Network [OSTI]

??An investigation of inflationary adjusted historical price trends of New Zealand pastoral farmers??? income and expenses over the past thirty years was investigated . The (more)

Aitken, Tim

2011-01-01T23:59:59.000Z

131

The Denver Energy Challenge- Serving Moderate Income Residents  

Broader source: Energy.gov [DOE]

Provides an overview of the Denver Energy Challenge and how services were expanded to moderate income residents including challenges and next steps.

132

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

133

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

134

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

135

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

136

COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE  

SciTech Connect (OSTI)

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance assessment, inclusion of dose calculations from collocated low-level waste in the boreholes for the individual protection requirements, further assessments of engineered barriers and conditions associated with the assurance requirements, and expansion of documentation provided for assessing the groundwater protection requirements. The Transuranic Waste Disposal Federal Review Group approved the performance assessment for Greater Confinement Disposal boreholes in 2001 and did not approve the Application of the Assurance Requirements. Remaining issues concerned with engineered barriers and the multiple aspects of the Assurance Requirements will be resolved at the time of closure of the Area 5 Radioactive Waste Management Site. This is the first completion and acceptance of a performance assessment for transuranic materials under the U.S. Department of Energy self-regulation. The Greater Confinement Disposal boreholes are only the second waste disposal configuration to meet the safety regulatory requirements of 40 CFR 191.

Colarusso, Angela; Crowe, Bruce; Cochran, John R.

2003-02-27T23:59:59.000Z

137

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

138

Is the American Dream Still Attainable? Income Inequality  

E-Print Network [OSTI]

lost the greatest amount of wealth in absolute terms, but the 50th percentile lost the highest percentage of their wealth. And Now The wealthiest largely have recovered wealth lost in the recession: movement of children above the education, occupation, income, and assets of their parents Capital Income

Wisconsin at Madison, University of

139

Integrating Photovoltaic Systems into Low-Income Housing Developments  

E-Print Network [OSTI]

Integrating Photovoltaic Systems into Low-Income Housing Developments: A Case Study on the Creation Integrating Photovoltaic Systems into Low-Income Housing Developments: A Case Study on the Creation of a New with integrating photovoltaic (PV) systems into existing financing models and the added cost to the new

140

Exact Measures of Income in a Hyperbolic Economy  

E-Print Network [OSTI]

Exact Measures of Income in a Hyperbolic Economy JOHN PEZZEY EEN0203 #12;Exact Measures of Income in a Hyperbolic Economy John C. V. Pezzey Centre for Resource and Environmental Studies Australian National.K. Draft of 23 January 2002 Abstract. Exact optimal paths are calculated for a closed economy with human

Pezzey, Jack

Note: This page contains sample records for the topic "rates disposable income" 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

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

SciTech Connect (OSTI)

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325

NSTec Environmental Programs

2010-09-14T23:59:59.000Z

142

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

143

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

144

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

145

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

146

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

147

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

148

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

149

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

150

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

151

Oil Prices, External Income, and Growth: Lessons from Jordan  

E-Print Network [OSTI]

This paper extends the long-run growth model of Esfahani et al. (2009) to a labour exporting country that receives large inflows of external income - the sum of remittances, FDI and general government transfers - from major oil exporting economies...

Mohaddes, Kamiar; Raissi, Mehdi

2011-12-08T23:59:59.000Z

152

Income and Health Spending: Evidence from Oil Price Shocks  

E-Print Network [OSTI]

Health expenditures as a share of GDP in the United States have more than tripled over the past half-century. A common conjecture is that this is a consequence of rising income. We investigate this hypothesis by instrumenting ...

Acemoglu, Daron

153

Minnesota Energy Resources (Gas)- Low-Income New Construction Rebates  

Broader source: Energy.gov [DOE]

Minnesota Energy Resources is now offering rebates for non-profits servicing low-income communities. New construction organizations can take advantage of rebates for efficient technologies if the...

154

Empire District Electric- Low Income New Homes Program  

Broader source: Energy.gov [DOE]

Empire District Electric offers rebates for the utilization of energy efficient measures and appliances in new, low-income homes. Rebates are available for several types of building insulation,...

155

Federal options for low-income electricity policy  

SciTech Connect (OSTI)

Protection of low-income consumers remains an important public policy concern in a restructuring electricity industry. Policies are needed to ensure that low-income households have enough affordable electricity to protect their health and safety, and that they are not victimized by unscrupulous suppliers. In this paper, the author presents three broad federal roles in setting low-income electricity policy, and discuss three more specific policy areas: universal service, electricity assistance, and health and safety. He discusses the key policy issues that arise when considering these potential federal initiatives and draw upon reviews of proposed low-income policies from restructuring proposals in eight states--California, Massachusetts, New Hampshire, New York, Pennsylvania, Rhode Island, Vermont, and Wisconsin.

Baxter, L.W. [Pew Charitable Trusts, Philadelphia, PA (United States)] [Pew Charitable Trusts, Philadelphia, PA (United States)

1998-06-01T23:59:59.000Z

156

Rate Schedules  

Broader source: Energy.gov [DOE]

One of the major responsibilities of Southeastern is to design, formulate, and justify rate schedules. Repayment studies prepared by the agency determine revenue requirements and appropriate rate...

157

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

158

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.

159

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...

160

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

162

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...

163

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...

164

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....

165

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

166

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

167

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,...

168

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...

169

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...

170

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...

171

DUSTMS-D: DISPOSAL UNIT SOURCE TERM - MULTIPLE SPECIES - DISTRIBUTED FAILURE DATA INPUT GUIDE.  

SciTech Connect (OSTI)

Performance assessment of a low-level waste (LLW) disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the source term). The focus of this work is to develop a methodology for calculating the source term. In general, the source term is influenced by the radionuclide inventory, the wasteforms and containers used to dispose of the inventory, and the physical processes that lead to release from the facility (fluid flow, container degradation, wasteform leaching, and radionuclide transport). Many of these physical processes are influenced by the design of the disposal facility (e.g., how the engineered barriers control infiltration of water). The complexity of the problem and the absence of appropriate data prevent development of an entirely mechanistic representation of radionuclide release from a disposal facility. Typically, a number of assumptions, based on knowledge of the disposal system, are used to simplify the problem. This has been done and the resulting models have been incorporated into the computer code DUST-MS (Disposal Unit Source Term-Multiple Species). The DUST-MS computer code is designed to model water flow, container degradation, release of contaminants from the wasteform to the contacting solution and transport through the subsurface media. Water flow through the facility over time is modeled using tabular input. Container degradation models include three types of failure rates: (a) instantaneous (all containers in a control volume fail at once), (b) uniformly distributed failures (containers fail at a linear rate between a specified starting and ending time), and (c) gaussian failure rates (containers fail at a rate determined by a mean failure time, standard deviation and gaussian distribution). Wasteform release models include four release mechanisms: (a) rinse with partitioning (inventory is released instantly upon container failure subject to equilibrium partitioning (sorption) with the waste form), (b) diffusion release.(release from either a cylindrical, spherical, or rectangular wasteform), (c) dissolution release (uniform release over time due to dissolution of the wasteform surface), and (d) solubility limited release. The predicated wasteform releases are corrected for radioactive decay and ingrowth. A unique set of container failure and wasteform release parameters can be specified for each control volume with a container. Contaminant transport is modeled through a finite-difference solution of the advective transport equation with sources (wasteform release and ingrowth) and radioactive decay. Although DUST-MS simulates one-dimensional transport, it can be used to simulate migration down to an aquifer and then transport in the aquifer by running the code twice. A special subroutine allows the flux into the aquifer from the first simulation to be input as the flux at the upstream boundary in the aquifer. This document presents the models used to calculate release from a disposal facility, verification of the model, and instructions on the use of the DUST-MS code. In addition to DUST-MS, a preprocessor, DUSTINMS, which helps the code user create input decks for DUST-MS and a post-processor, GRAFMS, which takes selected output files and plots them on the computer terminal have been written. Use of these codes is also described. In using DUST-MS, as with all computer models, the validity of the predictions relies heavily on the validity of the input parameters. Often, the largest uncertainties arise from uncertainty in the input parameters. Therefore, it is crucial to document and support the use of these parameters. The DUST-MS code, because of its flexibility and ability to compute release rates quickly, is extremely useful for screening to determine the radionuclide released at the highest rate, parameter sensitivity analysis and, with proper choice of the input parameters, provide upper bounds to release rates.

SULLIVAN, T.M.

2006-01-01T23:59:59.000Z

172

The Volunteer Income Tax Assistance (VITA) program provides free tax help to people with income under $58,000.  

E-Print Network [OSTI]

Free Tax Help The Volunteer Income Tax Assistance (VITA) program provides free tax help to people 28 March 6 March 20 March 27 April 3 Thursday March 1 March 29 Taxpayers interested in free help

Lawrence, Rick L.

173

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

174

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

175

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

176

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

177

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

178

Assessment of microbial processes on gas production at radioactive low-level waste disposal sites  

SciTech Connect (OSTI)

Factors controlling gaseous emanations from low level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide, and possible hydrogen from the site, stems from the inclusion of tritium and/or carbon-14 into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste material, primary emphasis of the study involved an examination of the biochemical pathways producing methane, carbon dioxide, and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Initial examination of the data indicates that the ecosystem is anaerobic. As the result of the complexity of the pathway leading to methane production, factors such as substrate availability, which limit the initial reaction in the sequence, greatly affect the overall rate of methane evolution. Biochemical transformations of methane, hydrogen and carbon dioxide as they pass through the soil profile above the trench are discussed. Results of gas studies performed at three commercial low level radioactive waste disposal sites are reviewed. Methods used to obtain trench and soil gas samples are discussed. Estimates of rates of gas production and amounts released into the atmosphere (by the GASFLOW model) are evaluated. Tritium and carbon-14 gaseous compounds have been measured in these studies; tritiated methane is the major radionuclide species in all disposal trenches studied. The concentration of methane in a typical trench increases with the age of the trench, whereas the concentration of carbon dioxide is similar in all trenches.

Weiss, A.J.; Tate, R.L. III; Colombo, P.

1982-05-01T23:59:59.000Z

179

Smooth Transitions into Medi-Cal: Ensuring Continuity of Coverage for Low Income Health Program Enrollees  

E-Print Network [OSTI]

Care Coverage Initiative (HCCI) enrollees with incomes above2012 Total Enrollment (HCCI + MCE) December 2012 Alameda

Lytle, Elizabeth C; Roby, Dylan H; Lucia, Laurel; Jacobs, Ken; Cabezas, Livier; Pourat, Naderah

2013-01-01T23:59:59.000Z

180

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

182

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

183

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

184

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

185

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

186

Energy Rating  

E-Print Network [OSTI]

Consistent, accurate, and uniform ratings based on a single statewide rating scale Reasonable estimates of potential utility bill savings and reliable recommendations on cost-effective measures to improve energy efficiency Training and certification procedures for home raters and quality assurance procedures to promote accurate ratings and to protect consumers Labeling procedures that will meet the needs of home buyers, homeowners, renters, the real estate industry, and mortgage lenders with an interest in home energy ratings

Cabec Conference; Rashid Mir P. E

2009-01-01T23:59:59.000Z

187

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

188

Effects of commercialized deer hunting arrangements on ranch organization, management, costs, and income--the Llano Basin of Texas  

E-Print Network [OSTI]

. To determine the returns possible from deer hunting leases on the representative ranches if the harvest rate recommen- dations of wildlife management personnel are followed. 18 This research ccntributes to Regional Research project W-79, "Economic Analysis... Income and Expense Summary Leasing Arrangements Used to Operate Shooting Preserves Description of Hunting Systems Season lease Day lease Season lease with doe hunting option Season and day lease combination Relative Profitability of the Various...

Forrest, Nathan Kelly

1968-01-01T23:59:59.000Z

189

Income over variable costs in a pasture based dairy industry  

E-Print Network [OSTI]

farms according to past production levels relative to past quota assignment. Quota is lost if production falls below assignment for more than three payment periods (4 weeks per period) in a twelve month interval. Extra quota becomes available... herds. Parameter Units Physical Income/Expense Income Quota milk Manufacture milk Stock sales Other liters/month liters/month NA1 NA A$/month A$/month A$/month A$/month Inputs Milking cows Dry cows Replacements Land Labor Grain Hay...

Phillips, Kenneth Robert

1990-01-01T23:59:59.000Z

190

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.

191

Estate-level facility provision and management in market-rate and resettlement coexisting housing compounds  

E-Print Network [OSTI]

Market-rate and resettlement coexisting housing compound (MRCHC) is a special model of mixed-income neighborhood merging with the dilapidated housing renewal in the major cities of China. The provision and management of ...

Bai, Jie, M.C.P. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

192

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

193

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

194

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

195

Ground-water flow and transport modeling of the NRC-licensed waste disposal facility, West Valley, New York  

SciTech Connect (OSTI)

This report describes a simulation study of groundwater flow and radionuclide transport from disposal at the NRC licensed waste disposal facility in West Valley, New York. A transient, precipitation driven, flow model of the near-surface fractured till layer and underlying unweathered till was developed and calibrated against observed inflow data into a recently constructed interceptor trench for the period March--May 1990. The results suggest that lateral flow through the upper, fractured till layer may be more significant than indicated by previous, steady state flow modeling studies. A conclusive assessment of the actual magnitude of lateral flow through the fractured till could however not be made. A primary factor contributing to this uncertainty is the unknown contribution of vertical infiltration through the interceptor trench cap to the total trench inflow. The second part of the investigation involved simulation of the migration of Sr-90, Cs-137 and Pu-239 from the one of the fuel hull disposal pits. A first-order radionuclide leach rate with rate coefficient of 10{sup {minus}6}/day was assumed to describe radionuclide release into the disposal pit. The simulations indicated that for wastes buried below the fractured till zone, no significant migration would occur. However, under the assumed conditions, significant lateral migration could occur for radionuclides present in the upper, fractured till zone. 23 refs., 68 figs., 12 tabs.

Kool, J.B.; Wu, Y.S. (HydroGeoLogic, Inc., Herndon, VA (United States))

1991-10-01T23:59:59.000Z

196

Trade and Income Exploiting Time Series in James Feyrer  

E-Print Network [OSTI]

Trade and Income ­ Exploiting Time Series in Geography James Feyrer Dartmouth College October 23. Rodriguez and Rodrik (2000) show that these results are not robust to controlling for omitted variables conferences for helpful comments. All errors are my own. james.feyrer@dartmouth.edu, Dartmouth College

Lotko, William

197

Poor Nutrition and Health Concerns in Low Income Population  

E-Print Network [OSTI]

and foodborne illness, reduced indigent health care costs and improved quality of life. Contact: Dean McPoor Nutrition and Health Concerns in Low Income Population An estimated one out of every six in 1995 as a cooperative endeavor among the Texas A&M AgriLife Extension Service, Texas Health and Human

198

Energy and Indoor Environmental Quality Retrofits in Low-Income  

E-Print Network [OSTI]

Buildings are responsible for about 40 percent of the total U.S. energy demand and carbon dioxide environmental measurements and collect energy consumption data. Based on analyses of the data collected fromEnergy and Indoor Environmental Quality Retrofits in Low-Income Apartments ENVIRONMENTAL ENERGY

199

Techniques for Dynamic and Prioritized Bandwidth Allocation On Incoming Links  

E-Print Network [OSTI]

to today, a network administrator has no control on the incoming traffic if the network service does]. This type of traffic appears in general to the network administrator (and to the high management activity of the organization will be called high priority traffic. As of today, a network administrator

200

Statistical Mechanics of Money, Income, Debt, and Energy Consumption  

E-Print Network [OSTI]

Statistical Mechanics of Money, Income, Debt, and Energy Consumption Physics Colloquium Presented in financial markets. Globally, data analysis of energy consumption per capita around the world shows@american.edu Similarly to the probability distribution of energy in physics, the probability distribution of money among

Hill, Wendell T.

Note: This page contains sample records for the topic "rates disposable income" 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

A Welcome to Incoming Optics Students from the Director  

E-Print Network [OSTI]

A Welcome to Incoming Optics Students from the Director It is my great pleasure to welcome you to The Institute of Optics, to join the training for the next generation of leaders in the field. Approximately half of all optics degrees awarded nationwide have been awarded by our institute since its founding

202

Family Moderate Income Homeowners In New York State  

Broader source: Energy.gov [DOE]

"Family Moderate Income Homeowners In New York State: Enhancing Resource Accessibility Through Process Improvement and Targeted Outreach," by Residential Energy Efficiency Solutions, July 10, 2012, Arlington, Virginia. Provides an overview of broadening accessibility to financing through process improvement and targeted outreach.

203

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

204

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...

205

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

206

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...

207

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

208

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

209

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...

210

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...

211

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...

212

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

213

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

214

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

215

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

216

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

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

217

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

218

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

219

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

220

Popular urban settlements in Athens : a comparative study of low income housing  

E-Print Network [OSTI]

This study is concerned with aspects of housing and urban development related to the lower income groups in the context of urbanization in Athens, Greece. It identifies and evaluates typical low income housing settlements ...

Kitsiou, Triada

1981-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "rates disposable income" 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

"Shelter within my reach" : medium rise apartment housing for the middle income group in Karachi, Pakistan  

E-Print Network [OSTI]

This thesis identifies the project development processes of medium rise (five storied or less) apartment housing built by the private formal sector, catering to the middle income groups in Karachi, Pakistan. Middle income ...

Mahmood, Saman, 1972-

1999-01-01T23:59:59.000Z

222

E-Print Network 3.0 - air pollution income Sample Search Results  

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

income Search Powered by Explorit Topic List Advanced Search Sample search results for: air pollution income Page: << < 1 2 3 4 5 > >> 1 Urban Form and Air Pollution in US Urban...

223

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

224

Conceptual problems of national income accounting in underdeveloped countries with emphasis on Pakistan  

E-Print Network [OSTI]

of changes in output, income and expenditures of the major sectors. Pinally, one is enabled by these means to study the responses of various economic groups to different conditions over a given time period. National income estimates are, therefore... followed Petty in the late seventeenth century, was considered to be the first scientific estimator of national income. His estimates included national income, national expenditure, and national savings, as well as the distributi. on of these aggregates...

Chowdhury, Abdur Rashid

1964-01-01T23:59:59.000Z

225

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

226

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

227

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect (OSTI)

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01T23:59:59.000Z

228

WORKING PAPER N 2007 -39 Income and wealth concentration in Spain in a  

E-Print Network [OSTI]

WORKING PAPER N° 2007 - 39 Income and wealth concentration in Spain in a historical and fiscal and Wealth Concentration in Spain in a Historical and Fiscal Perspective Facundo Alvaredo, Paris School of income and wealth in Spain over the 20th century using personal income and wealth tax return statistics

Boyer, Edmond

229

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

230

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

231

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

232

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

233

User`s Manual for the SOURCE1 and SOURCE2 Computer Codes: Models for Evaluating Low-Level Radioactive Waste Disposal Facility Source Terms (Version 2.0)  

SciTech Connect (OSTI)

The SOURCE1 and SOURCE2 computer codes calculate source terms (i.e. radionuclide release rates) for performance assessments of low-level radioactive waste (LLW) disposal facilities. SOURCE1 is used to simulate radionuclide releases from tumulus-type facilities. SOURCE2 is used to simulate releases from silo-, well-, well-in-silo-, and trench-type disposal facilities. The SOURCE codes (a) simulate the degradation of engineered barriers and (b) provide an estimate of the source term for LLW disposal facilities. This manual summarizes the major changes that have been effected since the codes were originally developed.

Icenhour, A.S.; Tharp, M.L.

1996-08-01T23:59:59.000Z

234

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

235

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

236

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

237

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

238

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

239

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

240

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

SciTech Connect (OSTI)

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.

NSTec Environmental Programs

2010-10-04T23:59:59.000Z

Note: This page contains sample records for the topic "rates disposable income" 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

Income distribution impacts of climate change mitigation policy in the Susquehanna River Basin Economy  

SciTech Connect (OSTI)

We examine the cost-side income distribution impacts of a carbon tax in the Susquehanna River Basin (SRB) Region of the United States utilizing a computable general equilibrium model. We find the aggregate impacts of a $25/ton carbon tax on the SRB economy are likely to be negative but modest-an approximately one-third of 1% reduction in Gross Regional Product (GRP) in the short-run and double that amount in the long-run. However, unlike many previous studies, we find that the carbon tax is mildly progressive as measured by income bracket changes, per capita equivalent variation, and Gini coefficient changes based on expenditure patterns. The dominant factors affecting the distributional impacts are the pattern of output, income and consumption impacts that affect lower income groups relatively less than higher income ones, an increase in transfer payments favoring lower income groups, and decreased corporate profits absorbed primarily by higher income groups.

Oladosu, Gbadebo A [ORNL

2007-01-01T23:59:59.000Z

242

Sustainable systems rating program: Marketing Green'' Building in Austin, Texas  

SciTech Connect (OSTI)

Four major resource issues for home construction were identified: water, energy, materials, and waste. A systems flow model was then developed that tracked the resource issues through interactive matrices in the areas of sourcing, processing, using, and disposing or recycling. This model served as the basis for a rating system used in an educational and marketing tool called the Eco-Home Guide.

Not Available

1991-12-01T23:59:59.000Z

243

Sustainable systems rating program: Marketing ``Green`` Building in Austin, Texas  

SciTech Connect (OSTI)

Four major resource issues for home construction were identified: water, energy, materials, and waste. A systems flow model was then developed that tracked the resource issues through interactive matrices in the areas of sourcing, processing, using, and disposing or recycling. This model served as the basis for a rating system used in an educational and marketing tool called the Eco-Home Guide.

Not Available

1991-12-01T23:59:59.000Z

244

System Integration System Demonstration Low-Rate Initial Production Acquisition  

E-Print Network [OSTI]

, & Logistics Life Cycle Management Framework FOC IOC Full-Rate Production/Deployment MS B System Development its total life cycle. Dispose of the system in the most cost-effective manner at the end of its useful Capabilities Integration & Development System VCJCS Oversight CJCSI 3170.01E Defense Acquisition System USD

Rhoads, James

245

Report on waste burial charges. Escalation of decommissioning waste disposal costs at low-level waste burial facilities, Revision 4  

SciTech Connect (OSTI)

One of the requirements placed upon nuclear power reactor licensees by the U.S. Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fourth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991 and 1993, superseding the values given in the May 1993 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1994 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

Not Available

1994-06-01T23:59:59.000Z

246

Report on waste burial charges: Escalation of decommissioning waste disposal costs at Low-Level Waste Burial facilities. Revision 5  

SciTech Connect (OSTI)

One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fifth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991, 1993, and 1994, superseding the values given in the June 1994 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1995 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

NONE

1995-08-01T23:59:59.000Z

247

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

248

Laboratory Experiments to Stimulate CO(2) Ocean Disposal  

SciTech Connect (OSTI)

This Technical Progress Report summarizes activities conducted over the period 8/16/96-2/15/97 as part of this project. 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 is 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. Critical technical uncertainties of ocean disposal of CO{sub 2} will be addressed by performing experiments that: (1) characterize size spectra and velocities of a dispersed CO{sub 2} phase in the near-field of a discharge jet; and (2) estimate rates of mass transfer from dissolving droplets of liquid CO{sub 2} encased in a thin hydrate shell. Experiments will be conducted in a laboratory facility that can reproduce conditions in the ocean to depths of 600 m (1,969 ft). Between 8/16/96 and 2/15/97, activities focused on modifications to the experimental apparatus and the testing of diagnostics. Following completion of these tasks, experiments will be initiated and will continue through the end of the 36 month period of performance. Major accomplishments of this reporting period were: (1) delivery, set-up, and testing of the PDPA (Phase Doppler Particle Analyzer), which will be the principal diagnostic of the continuous CO{sub 2} jet injection tests; (2) presentation of research papers and posters at the 212th American Chemical Society National Meeting and the Third International Conference on Carbon Dioxide Removal; (3) participation in the 4th Expert Workshop on Ocean Storage of Carbon Dioxide; (4) execution of an Agreement with ABB Management, Ltd. to support and extend the activities of this grant; and (5) initiation of research collaborations with Dr. P.M. Haugen of the University of Bergen, Norway, and Dr. A. Yamasaki of the National Institute of Materials and Chemical Research, Japan.

Masutani, S.M.

1997-03-12T23:59:59.000Z

249

Rate schedule  

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 MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, andEpidermal Growth Factor. |INCIDENCET3PACI-T3Rate

250

Irradiated Beryllium Disposal Workshop, Idaho Falls, ID, May 29-30, 2002  

SciTech Connect (OSTI)

In 2001, while performing routine radioactive decay heat rate calculations for beryllium reflector blocks for the Advanced Test Reactor (ATR), it became evident that there may be sufficient concentrations of transuranic isotopes to require classification of this irradiated beryllium as transuranic waste. Measurements on samples from ATR reflector blocks and further calculations confirmed that for reflector blocks and outer shim control cylinders now in the ATR canal, transuranic activities are about five times the threshold for classification. That situation implies that there is no apparent disposal pathway for this material. The problem is not unique to the ATR. The High Flux Isotope Reactor at Oak Ridge National Laboratory, the Missouri University Research Reactor at Columbia, Missouri and other reactors abroad must also deal with this issue. A workshop was held in Idaho Falls Idaho on May 29-30, 2002 to acquaint stakeholders with these findings and consider a path forward in resolving the issues attendant to disposition of irradiated material. Among the findings from this workshop were (1) there is a real potential for the US to be dependent on foreign sources for metallic beryllium within about a decade; (2) there is a need for a national policy on beryllium utilization and disposition and for a beryllium coordinating committee to be assembled to provide guidance on that policy; (3) it appears it will be difficult to dispose of this material at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico due to issues of Defense classification, facility radioactivity inventory limits, and transportation to WIPP; (4) there is a need for a funded DOE program to seek resolution of these issues including research on processing techniques that may make this waste acceptable in an existing disposal pathway or allow for its recycle.

Longhurst, Glen Reed; Anderson, Gail; Mullen, Carlan K; West, William Howard

2002-07-01T23:59:59.000Z

251

Evaluating the income and employment impacts of gas cooling technologies  

SciTech Connect (OSTI)

The purpose of this study is to estimate the potential employment and income benefits of the emerging market for gas cooling products. The emphasis here is on exports because that is the major opportunity for the U.S. heating, ventilating, and air-conditioning (HVAC) industry. But domestic markets are also important and considered here because without a significant domestic market, it is unlikely that the plant investments, jobs, and income associated with gas cooling exports would be retained within the United States. The prospects for significant gas cooling exports appear promising for a variety of reasons. There is an expanding need for cooling in the developing world, natural gas is widely available, electric infrastructures are over-stressed in many areas, and the cost of building new gas infrastructure is modest compared to the cost of new electric infrastructure. Global gas cooling competition is currently limited, with Japanese and U.S. companies, and their foreign business partners, the only product sources. U.S. manufacturers of HVAC products are well positioned to compete globally, and are already one of the faster growing goods-exporting sectors of the U.S. economy. Net HVAC exports grew by over 800 percent from 1987 to 1992 and currently exceed $2.6 billion annually (ARI 1994). Net gas cooling job and income creation are estimated using an economic input-output model to compare a reference case to a gas cooling scenario. The reference case reflects current policies, practices, and trends with respect to conventional electric cooling technologies. The gas cooling scenario examines the impact of accelerated use of natural gas cooling technologies here and abroad.

Hughes, P.J. [Oak Ridge National Lab., TN (United States); Laitner, S.

1995-03-01T23:59:59.000Z

252

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

253

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.

254

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

255

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

256

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

257

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

258

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

259

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

260

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

262

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

263

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

264

Trapped surfaces in vacuum arising dynamically from mild incoming radiation  

E-Print Network [OSTI]

In this paper, we study the "minimal requirement" on the incoming radiation that guarantees a trapped surface to form in vacuum. First, we extend the region of existence in Christodoulou's theorem on the formation of trapped surfaces and consequently show that the lower bound required to form a trapped surface can be relaxed. Second, we demonstrate that trapped surfaces form dynamically from a class of initial data which are large merely in a scaling-critical norm. This result is motivated in part by the scaling in Christodoulou's formation of trapped surfaces theorem for the Einstein-scalar field system in spherical symmetry.

Xinliang An; Jonathan Luk

2014-09-22T23:59:59.000Z

265

A treatment of controversial income and expense items  

E-Print Network [OSTI]

nmdatioa of iaprovccxents in aogounting preoties then is any ether hind of study. s The inocsce stat&meat has, in the past? boon relegated to the bacdcground uhile the bolsnoe sheet bos undergone a waxy olose ?erntinye Xt is ocQ. y of 8 odmpsrstively... bayou bases whioh invite eri tiois@. Xt is e~aLp important that eu effort be made bo establish stsndar4s whioh weal ayyeal to yersons eoneornea with aeooante as logical anC reasonable 1 Probabip the greatest writ%eisa of moat income statemeata, ia...

Oliver, John Eoff

1937-01-01T23:59:59.000Z

266

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

267

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

268

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

269

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

270

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

271

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...

272

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...

273

SPECIAL ANALYSIS FOR SLIT TRENCH DISPOSAL OF THE REACTOR PROCESS HEAT EXCHANGERS  

SciTech Connect (OSTI)

The Savannah River National Laboratory (SRNL), in response to a request from Solid Waste Management (SWM), conducted a Special Analysis (SA) to evaluate the performance of nineteen heat exchangers that are to be disposed in the E-Area low level waste facility Slit Trench 9 (ST 9). Although these nineteen heat exchangers were never decontaminated, the majority of the radionuclides in the heat exchanger inventory list were determined to be acceptable for burial because they are less than the 'generic' waste form inventory limits given in the 2008 Performance Assessment (PA) (WSRC, 2008). However, as generic waste, the H-3 and C-14 inventories resulted in unacceptable sum-of-fractions (SOFs). Initial scoping analyses performed by SRNL indicated that if alterations were made to certain external nozzles to mitigate various potential leak paths, acceptable SOFs could be achieved through the use of a 'Special' waste form. This SA provides the technical basis for this new 'Special' waste form and provides the inventory limits for H-3 and C-14 for these nineteen heat exchangers such that the nineteen heat exchangers can be disposed in ST 9. This 'Special' waste form is limited to these nineteen heat exchangers in ST 9 and applies for H-3 and C-14, which are designated as H-3X and C-14X, respectively. The SA follows the same methodology used in the 2008 PA and the 2008 SA except for the modeling enhancements noted below. Infiltration rates above the heat exchangers are identical to those used in the 2008 PA; however, flow through the heat exchangers is unique. Because it is unknown exactly how sealed heat exchanger openings will perform and how surface and embedded contaminants will be released, multiple base cases or scenarios were established to investigate a set of performances. Each scenario consists of flow options (based on the performance of sealed openings) and a near-field release of contaminants (based on corrosion and diffusion performance). Two disposal configurations were analyzed where heat exchangers were assumed to be disposed four across and five lengthwise (the 4x5 configuration, with one empty) and three across and seven lengthwise (the 3x7 configuration, with two empty). A large range of conditions was considered. For example, peak well concentrations at the 100-m boundary for H-3 are shown in Figure ES-1 for a wide range of configurations (i.e. release mechanism and degree of sealing options). The maximum contaminant level (MCL) and a 10% SOF goal for H-3 are also shown. The 10% goal was based on an estimated volume fraction that these nineteen heat exchangers would consume in ST 9 and was solely used for scoping purposes to assess disposal feasibility and sealing requirements. Because various line breaks and poor sealing greatly exceeded that 10% goal, the determination was made that mitigating activities were needed, such as protection from line breaks and better sealing. An initial set of scenarios was run to assess the requirements for sealing the heat exchanger openings and the need to ensure that the sealed heat exchangers stayed sealed during transit and disposal operations. After discovering that such mitigating activities were required, additional scenarios were run that included the mitigating activities. Scenarios deemed to have a very low probability of occurrence were excluded from consideration for calculating inventory limits (for example, those scenarios that assumed an instantaneous release of contaminants along with poor sealing). The SA used the most recent K{sub d} values for the C-14 analyses and the most recent Dose Conversion Factors for H-3 and C-14 which have been updated since the 2008 PA was issued. This SA took into account the location and the disposal timing of these heat exchangers. The disposal location is within a small area of the overall Slit Trench unit (about 6% of the total) and is behind a line that is 200 ft from the down-gradient edge of ST 9. The disposal timing is assumed to be after July 1, 2012 (because disposals cannot occur until this document is approved and miti

Hamm, L.; Collard, L.; Aleman, S.; Gorensek, M.; Butcher, T.

2012-06-18T23:59:59.000Z

274

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

275

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

276

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

277

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

278

Facts and Figures January 2007 INCOME AND EXPENDITURE (Excluding Press, CA & Trusts) 2005-06  

E-Print Network [OSTI]

Facts and Figures January 2007 INCOME AND EXPENDITURE (Excluding Press, CA & Trusts) 2005-06 2004,928 Breakdown of Research Grant Income 2005-06 £'000 % £'000 Total staff 8602 8570 8,623 Research Councils 89,095 Total 203,886 188,711 Total respondents 2,890 100.0% 3,227 100.0 Breakdown of HEFCE/TDA Income 2005-06

Travis, Adrian

279

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

280

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.

Note: This page contains sample records for the topic "rates disposable income" 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

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.

282

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

283

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

284

California Solar Initiative- Low-Income Solar Water Heating Rebate Program  

Broader source: Energy.gov [DOE]

The California Public Utilities Commission (CPUC) voted in October 2011 to create the California Solar Initiative (CSI) Thermal Low-Income program for single and multifamily residential properties....

285

BC Hydro Brings Energy Savings to Low-Income Families in Canada...  

Energy Savers [EERE]

needs described in their application. Other BC Hydro incentives not based on income include a rebate program for insulation, draft-proof measures, heat pumps, and water heaters...

286

Effect of Income on Appliances in U.S. Households, The  

Reports and Publications (EIA)

Entails how people live, the factors that cause the most differences in home lifestyle, including energy use in geographic location, socioeconomics and household income.

2004-01-01T23:59:59.000Z

287

Honduras-Program for Scaling Up Renewable Energy in Low Income...  

Open Energy Info (EERE)

Kenya Specific Documents4 Maldives Specific Documents5 Mali Specific Documents6 Nepal Specific Documents7 Overview "The Scaling-Up Renewable Energy Program for Low Income...

288

Kenya-Program for Scaling Up Renewable Energy in Low Income Countries...  

Open Energy Info (EERE)

Kenya Specific Documents4 Maldives Specific Documents5 Mali Specific Documents6 Nepal Specific Documents7 Overview "The Scaling-Up Renewable Energy Program for Low Income...

289

Maldives-Program for Scaling Up Renewable Energy in Low Income...  

Open Energy Info (EERE)

Kenya Specific Documents4 Maldives Specific Documents5 Mali Specific Documents6 Nepal Specific Documents7 Overview "The Scaling-Up Renewable Energy Program for Low Income...

290

Mali-Program for Scaling Up Renewable Energy in Low Income Countries...  

Open Energy Info (EERE)

Kenya Specific Documents4 Maldives Specific Documents5 Mali Specific Documents6 Nepal Specific Documents7 Overview "The Scaling-Up Renewable Energy Program for Low Income...

291

Nepal-Program for Scaling Up Renewable Energy in Low Income Countries...  

Open Energy Info (EERE)

Nepal UN Region Southern Asia References Program for Scaling Up Renewable Energy in Low Income Countries (SREP)1 Ethiopia Specific Documents2 Honduras Specific Documents3...

292

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

293

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

294

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

295

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

296

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

297

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

SciTech Connect (OSTI)

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

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

2011-03-01T23:59:59.000Z

298

Appraisal of a cementitious material for waste disposal: Neutron imaging studies of pore structure and sorptivity  

SciTech Connect (OSTI)

Cementitious materials are conventionally used in conditioning intermediate and low level radioactive waste. In this study a candidate cement-based wasteform has been investigated using neutron imaging to characterise the wasteform for disposal in a repository for radioactive materials. Imaging showed both the pore size distribution and the extent of the cracking that had occurred in the samples. The rate of the water penetration measured both by conventional sorptivity measurements and neutron imaging was greater than in pastes made from Ordinary Portland Cement. The ability of the cracks to distribute the water through the sample in a very short time was also evident. The study highlights the significant potential of neutron imaging in the investigation of cementitious materials. The technique has the advantage of visualising and measuring, non-destructively, material distribution within macroscopic samples and is particularly useful in defining movement of water through the cementitious materials.

McGlinn, Peter J., E-mail: pjm@ansto.gov.a [Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights, NSW 2234 (Australia); Beer, Frikkie C. de [South African Nuclear Energy Corporation (Necsa), Church Street West Extension, Pelindaba, Brits District, Pretoria 0001 (South Africa); Aldridge, Laurence P. [Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights, NSW 2234 (Australia); Radebe, Mabuti J.; Nshimirimana, Robert [South African Nuclear Energy Corporation (Necsa), Church Street West Extension, Pelindaba, Brits District, Pretoria 0001 (South Africa); Brew, Daniel R.M.; Payne, Timothy E.; Olufson, Kylie P. [Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights, NSW 2234 (Australia)

2010-08-15T23:59:59.000Z

299

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

300

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

302

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

303

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

304

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

305

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

306

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

307

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

308

Low-income communities : technological strategies for nurturing community, empowerment and self-sufficiency at a low-income housing development  

E-Print Network [OSTI]

There are a number of historically familiar and unfamiliar forces at work in low-income communities in the United States. Recurrent forces include rapidly changing economic and demographic trends, Welfare Reform, and the ...

O'Bryant, Richard Louis, 1964-

2004-01-01T23:59:59.000Z

309

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

310

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

311

Marketing Compost A Guide for Compost Producers in Low and Middle-Income Countries  

E-Print Network [OSTI]

Marketing Compost A Guide for Compost Producers in Low and Middle-Income Countries Sandec #12;Marketing Compost A Guide for Compost Producers in Low and Middle-Income Countries Jonathan Rouse Introduction 7 2 Background 11 2.1 What is marketing? 11 2.2 Why is marketing important for compost producers

Wehrli, Bernhard

312

Social Welfare Policy and Public Assistance for Low-Income Substance Abusers  

E-Print Network [OSTI]

income and health care benefits for many low- income substance abusers. This paper examines functioning has been a point of contention among politicians, physicians, and sub- stance abuse treatment. Individuals with substan- tiated claims were mandated to substance abuse treatment, to having a representative

de Lijser, Peter

313

Determinants and Income Effects of Commuting and Migration An empirical analysis for Germany after Unification  

E-Print Network [OSTI]

Determinants and Income Effects of Commuting and Migration An empirical analysis for Germany after differentials between East and West Germany led to massive commuting and migration flows. In this paper we: Human capital and income, Germany, commuting, migration, GSOEP JEL No.: J31, J61, O15 Address: Institute

Pfeifer, Holger

314

China's Income Distribution, 1985-2001 Ximing Wu* and Jeffrey M. Perloff**  

E-Print Network [OSTI]

China's Income Distribution, 1985-2001 Ximing Wu* and Jeffrey M. Perloff** February, 2005 We Bureau of Statistics of China, for explaining many features of the Chinese urban survey. Ximing Wu@are.berkeley.edu. #12;Abstract We employ a new method to estimate China's income distributions using publicly available

Perloff, Jeffrey M.

315

Enabling energy efficiency for low-income housing in Developing countries using MIT Design Advisor  

E-Print Network [OSTI]

There is a great need to improve energy efficiency of low-income housing, since people who can afford it least have to pay a significant portion of their income to make their homes more habitable or else live with greater ...

Ali, Zehra (Zehra Hyder)

2009-01-01T23:59:59.000Z

316

Incomes in South Africa since the fall of Apartheid Murray Leibbrandt  

E-Print Network [OSTI]

Incomes in South Africa since the fall of Apartheid by Murray Leibbrandt University of Cape Town in South Africa between 1995 and 2000. We document substantial declines--on the order of 40%--in real Africa #12;Incomes in South Africa since the fall of Apartheid Murray Leibbrandt University of Cape Town

Sadoulet, Elisabeth

317

ORNL/CON-486 WEATHERIZING THE HOMES OF LOW-INCOME  

E-Print Network [OSTI]

ORNL/CON-486 WEATHERIZING THE HOMES OF LOW-INCOME HOME ENERGY ASSISTANCE PROGRAM CLIENTS Government or any agency thereof. #12;ORNL/CON-486 WEATHERIZING THE HOMES OF LOW-INCOME HOME ENERGY............................................................................................................................17 APPENDIX A RESIDENTIAL NATURAL GAS AND NO. 2 HEATING OIL PRICES AND HEATING DEGREE DAYS

318

Compact disposal of high-energy electron beams using passive or laser-driven plasma decelerating stage  

SciTech Connect (OSTI)

A plasma decelerating stage is investigated as a compact alternative for the disposal of high-energy beams (beam dumps). This could benefit the design of laser-driven plasma accelerator (LPA) applications that require transportability and or high-repetition-rate operation regimes. Passive and laser-driven (active) plasma-based beam dumps are studied analytically and with particle-in-cell (PIC) simulations in a 1D geometry. Analytical estimates for the beam energy loss are compared to and extended by the PIC simulations, showing that with the proposed schemes a beam can be efficiently decelerated in a centimeter-scale distance.

Bonatto, A.; Schroeder, C.B.; Vay, J.-L.; Geddes, C.R.; Benedetti, C.; Esarey and, E.; Leemans, W.P.

2014-07-13T23:59:59.000Z

319

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

320

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

Note: This page contains sample records for the topic "rates disposable income" 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 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

322

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

323

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

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 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

325

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

326

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

327

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

328

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

329

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

330

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

331

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

332

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

333

Investigating the book-tax income gap : factors which affect the gap and details regarding its most significant component  

E-Print Network [OSTI]

(cont.) In total, my thesis suggests that recent changes in the book-tax income gap may be exogenous and transitory, due to changes to the calculation of book income, general business conditions or other factors which ...

Seidman, Jeri

2008-01-01T23:59:59.000Z

334

Total Gamma Count Rate Analysis Method for Nondestructive Assay Characterization  

SciTech Connect (OSTI)

A new approach to nondestructively characterize waste for disposal, based on total gamma response, has been developed at the Idaho Cleanup Project by CH2M-WG Idaho, LLC and Idaho State University, and is called the total gamma count rate analysis method. The total gamma count rate analysis method measures gamma interactions that produce energetic electrons or positrons in a detector. Based on previous experience with waste assays, the radionuclide content of the waste container is then determined. This approach potentially can yield minimum detection limits of less than 10 nCi/g. The importance of this method is twofold. First, determination of transuranic activity can be made for waste containers that are below the traditional minimum detection limits. Second, waste above 10 nCi/g and below 100 nCi/g can be identified, and a potential path for disposal resolved.

Cecilia R. Hoffman; Yale D. Harker

2006-03-01T23:59:59.000Z

335

1998 report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect (OSTI)

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

Black, D.G.

1998-04-10T23:59:59.000Z

336

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

337

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

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, 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

339

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

340

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

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


341

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

342

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

343

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

344

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

345

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

346

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

347

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

348

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

349

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

350

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

351

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

352

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

353

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

354

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

355

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

356

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

357

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

358

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

359

[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

360

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

362

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

363

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...

364

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...

365

Retirement income options using your SFU Group LIF/RRIF  

E-Print Network [OSTI]

Civic Sedan DX with air conditioning ** Average price for a detached bungalow in Canada, as at September TODAY Value of money ­ historical comparison The rule of 72: Divide your estimated inflation rate

366

Chlorite Dissolution Rates  

SciTech Connect (OSTI)

Spreadsheets provides measured chlorite rate data from 100 to 300C at elevated CO2. Spreadsheet includes derived rate equation.

Carroll, Susan

2013-07-01T23:59:59.000Z

367

Chlorite Dissolution Rates  

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

Spreadsheets provides measured chlorite rate data from 100 to 300C at elevated CO2. Spreadsheet includes derived rate equation.

Carroll, Susan

368

The Interest Rate Conundrum  

E-Print Network [OSTI]

Flows and US Interest Rates, NBER Working Paper No 12560. [Working Paper # 2008 -03 The Interest Rate Conundrum Roger

Craine, Roger; Martin, Vance L.

2009-01-01T23:59:59.000Z

369

Low-income housing : alternative strategies for building construction and project control  

E-Print Network [OSTI]

Housing low-income groups, who cannot afford even the most minimal shelter, remains a dominant issue in most developing countries. However, all the solutions advanced so far depend on large investments, either by the ...

Sultan, Javed

1982-01-01T23:59:59.000Z

370

Impacts of Climate Conditions and Adaptations on Agricultural Output and Household Income in Inner Mongolia, China  

E-Print Network [OSTI]

between rural agricultural production/income generation, climate factors and adaptive activities in the dryland system. Two respective multiple regression models on grain and livestock production were built with secondary panel data in Inner Mongolia from...

Chen, Wenjuan

2014-07-31T23:59:59.000Z

371

Promoting Enrollment of Low Income Health Program Participants in Covered California  

E-Print Network [OSTI]

5. Estimate based on LIHP-HCCI enrollment trends from theCare Coverage Initiative (HCCI) enrollees with incomes abovechose to offer services to HCCI enrollees. 3 In December

Lytle, Elizabeth C.; Roby, Dylan H.; Lucia, Laurel; Cabezas, Livier; Pourat, Nadereh

2013-01-01T23:59:59.000Z

372

City of Tallahassee Utilities- Low-Income Energy Efficiency Grant Programs  

Broader source: Energy.gov [DOE]

City of Tallahassee Utilities offers two different grants that encourage low-income residents to improve the energy efficiency of homes. Both programs require a free home energy audit to be...

373

Equitable economic energy efficiency : creating good jobs in low-income efficiency programming  

E-Print Network [OSTI]

Energy efficiency is an important consideration in energy policy-making. So, a federal program aimed at funding "energy efficiency retrofits" for low-income households could be an important step in increasing the overall ...

Sarin, Amit

2009-01-01T23:59:59.000Z

374

Low-income communities in World Heritage Cities : revitalizing neighborhoods in Tunis and Quito  

E-Print Network [OSTI]

Since the 1970s, international preservation and funding agencies have promoted revitalization projects in developing countries aiming to, among other things, benefit low-income communities. For the most part, these projects ...

Young, T. Luke, 1972-

2000-01-01T23:59:59.000Z

375

Community transportation : alternative transportation provision in a low-income neighborhoods in southeast Atlanta  

E-Print Network [OSTI]

Regional transit agencies are ineffective at meeting many of the basic transportation needs of a clustered "Study Area" of low-income Atlanta neighborhoods. For transit dependant residents in the Study Area, getting to the ...

Alexander, James W., 1977-

2004-01-01T23:59:59.000Z

376

Higher occupancy humanism : the trade-offs for encouraging middle income housing in a global city  

E-Print Network [OSTI]

In high density urban areas where the land acquisition and construction cost components are significant relative to total development costs, the market typically supplies a high-income housing product in order to justify ...

Konishi, Ryunosuke, 1975-

2003-01-01T23:59:59.000Z

377

The relationship between income, health status, and health expenditures in the United States  

E-Print Network [OSTI]

The relationship between income and health has important implications for policy makers and businesses, and will continue to receive attention as healthcare reform takes hold in the U.S. Most existing literature looks at ...

Bueno, David

2011-01-01T23:59:59.000Z

378

Global economic changes and income inequality: a test of four competing models  

E-Print Network [OSTI]

support relationships specified by dependency theory, world system theory, and political democracy theory. When both cohorts are analyzed simultaneously, trade dependency is positively related to income inequality, lending support to dependency theory...

Morris, Theresa Marie

1996-01-01T23:59:59.000Z

379

Urban settlement design, Seoul, Korea : a comparative study for low-income housing  

E-Print Network [OSTI]

The study proposes an alternative design approach for urban dwelling environments of the low-income sectors in Seoul, Korea, based upon a comparative evaluation of the physical and socio-economic performance of the existing ...

Je, Hae-Seong

1982-01-01T23:59:59.000Z

380

New Hampshire Electric Co-Op- Low-Income Energy Assistance Grant Program  

Broader source: Energy.gov [DOE]

The Energy Assistance Program is designed to help NHEC's income-qualified members manage energy use with the goal of lowering total energy costs. Qualified members living in an apartment or house,...

Note: This page contains sample records for the topic "rates disposable income" 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

The forgotten class : reconceptualizing contemporary middle-income housing in New York City  

E-Print Network [OSTI]

New York City's costly real estate poses housing affordability challenges for not only low- or even moderate-income households, but also for the so-called "middle class." Because New York is predominantly a renter's market, ...

Milchman, Karina (Karina Faye)

2013-01-01T23:59:59.000Z

382

Income generation through zakat : the Islamization impact on Malaysian religious institution  

E-Print Network [OSTI]

The aim of this thesis is to examine how the Islamization phenomenon has influenced zakat. The study shows that the distribution of the fund for income generation is a manifestation of the impact of Islamization on the ...

Sarif, Suhaili

2014-07-03T23:59:59.000Z

383

Low income housing tax credit properties : non-profit disposition strategies in the Commonwealth  

E-Print Network [OSTI]

This thesis examines how non-profit owners in Massachusetts have maintained affordability and ownership of Low-Income Housing Tax Credit (LIHTC) properties after the initial fifteen-year compliance period, at the lowest ...

Lew-Hailer, Lillian

2007-01-01T23:59:59.000Z

384

The Low-Income Housing Tax Credit : HERA, ARRA and beyond  

E-Print Network [OSTI]

The Low-Income Housing Tax Credit (LIHTC) has arguably been the most successful government subsidy to finance affordable housing. Since its creation in the Tax Reform Act of 1986 as Internal Revenue Code (IRC) Section 42, ...

Korb, Jason (Jason Bryan Patricof)

2009-01-01T23:59:59.000Z

385

Predicting School Readiness for Low-Income Children With Disability Risks Identified Early.  

E-Print Network [OSTI]

This study examined school readiness at kindergarten entry for low-income children whose disability indicators were identified before age 3. Data were collected as part ofthe Early Head Start Research and Evaluation ...

Jeon, Hyun-Joo; Peterson, Carla A.; Wall, Shavaun; Carta, Judith J.; Gayle, Luze; Eshbaugh, Elaine M.; Swanson, Mark

2011-01-01T23:59:59.000Z

386

Causes, effects, and implications of subletting : experiences from low-income neighborhoods in Third World cities  

E-Print Network [OSTI]

In recent years increasing numbers of low-income families in Third World cities have found it necessary to share housing accommodation. Those with access to land may be unable to afford to build their house or to pay the ...

Bailey, Susan Ruth

1987-01-01T23:59:59.000Z

387

Key worker housing : a demand analysis of middle-income workforce housing in eastern Massachusetts  

E-Print Network [OSTI]

The Boston Metropolitan Area is one of the most expensive places to live in the United States. In recent years studies have speculated that middle-income workers have had to endure increased commute times as they have moved ...

Sacks, Sean D

2005-01-01T23:59:59.000Z

388

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

389

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

390

FREE TAX FILING VITA is a program sponsored by the IRS offering income tax preparation for  

E-Print Network [OSTI]

FREE TAX FILING VITA is a program sponsored by the IRS offering income tax preparation for families with income less than $58,000 for FREE. WALK-IN ONLY (at least 1 hour before closing) MORE INFO: csufvita@gmail.com / 657-278-8681 Free tax filing starts from Jan 31 to Apr 12 We are closed on Feb 1, Apr 3, 4 & 5

de Lijser, Peter

391

Making It Happen: Achieving Energy Efficiency in Multi-Family Buildings Housing Low-Income Tenants  

E-Print Network [OSTI]

convert single-family, commercial, industrial, and public buildings into energy efficient structures have not been readily transferable to multi-family buildings. Consequently, with few exceptions, the knot has remained a complex tangle of variables...-family residences owned by low-income people, they undoubtedly would object to wide- spread public investment in commercial, income- producing properties. The excepi~ion to this generalization is the national Solar Energy and Energy Conservation Bank...

Haun, C. R.

1985-01-01T23:59:59.000Z

392

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

393

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

394

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

395

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

396

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

397

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

398

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

399

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

400

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

Note: This page contains sample records for the topic "rates disposable income" 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

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

402

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

403

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

404

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

405

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

406

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

407

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

408

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

409

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

410

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

411

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

412

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

413

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

414

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

415

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

416

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

417

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

418

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

419

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

420

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

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421

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

422

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

423

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

424

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

425

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

426

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

427

Disposal Of Irradiated Cadmium Control Rods From The Plumbrook Reactor Facility  

SciTech Connect (OSTI)

Innovative mixed waste disposition from NASA's Plum Brook Reactor Facility was accomplished without costly repackaging. Irradiated characteristic hardware with contact dose rates as high as 8 Sv/hr was packaged in a HDPE overpack and stored in a Secure Environmental Container during earlier decommissioning efforts, awaiting identification of a suitable pathway. WMG obtained regulatory concurrence that the existing overpack would serve as the macro-encapsulant per 40CFR268.45 Table 1.C. The overpack vent was disabled and the overpack was placed in a stainless steel liner to satisfy overburden slumping requirements. The liner was sealed and placed in shielded shoring for transport to the disposal site in a US DOT Type A cask. Disposition via this innovative method avoided cost, risk, and dose associated with repackaging the high dose irradiated characteristic hardware. In conclusion: WMG accomplished what others said could not be done. Large D and D contractors advised NASA that the cadmium control rods could only be shipped to the proposed Yucca mountain repository. NASA management challenged MOTA to find a more realistic alternative. NASA and MOTA turned to WMG to develop a methodology to disposition the 'hot and nasty' waste that presumably had no path forward. Although WMG lead a team that accomplished the 'impossible', the project could not have been completed with out the patient, supportive management by DOE-EM, NASA, and MOTA. (authors)

Posivak, E.J.; Berger, S.R.; Freitag, A.A. [WMG, Inc., Peekskill, NY (United States)

2008-07-01T23:59:59.000Z

428

Tank waste remediation system retrieval and disposal mission -- Phase 1: Financial analysis  

SciTech Connect (OSTI)

In Section 1.0, an overview of the Financial Analysis was provided and summarized in Table 1 for both the Retrieval and Disposal program and the TWRS project life cycle. A table recaps the pre-Phase 1B analysis budget requirements as discussed in previous sections. Another table in this section shows a similar build-up of costs and the impact of proposed offsets and increases to the pre-Phase 1B analysis. The issues concerning the increased requirements in FY 1998/1999 and the recommended adjustments were discussed. The Phase 1B Program as recommended is achievable. Specific recommendations are as follows: (a) Adopt the revised project baseline as presented in the cited tables; (b) Incorporate the $248.5 million in allowances for risk into the baseline; (c) Develop detailed action plans to realize the costs reduction opportunities; (d) Incorporate site indirect and benefits reduction rates into baseline; (e) Delay non-critical path scope which can be moved beyond FY 1999, as indicated: and (f) Renegotiate the Tri-Party Agreement milestones associated with the current compliance unfunded list for FY 1998.

Bickford, J.C.

1998-01-06T23:59:59.000Z

429

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

430

Effective Rate Period  

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

of the FY Mid-Year Change 10012013 - 03312014 04012014 - 09302014 Power Rates Annual Revenue Requirement Rate Schedule Power Revenue Requirement 73,441,557...

431

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

432

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site  

SciTech Connect (OSTI)

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here. Parameters necessary for estimating surface contaminant flux due to native plants expected to inhabit the NTS RWMSS are developed in this report. The model is specific to the plant communities found at the NTS and is designed for both short-term (<1,000 years) and long-term (>1,000 years) modeling efforts. While the model has been crafted for general applicability to any NTS PA, the key radionuclides considered are limited to the transuranic (TRU) wastes disposed of at the NTS.

BROWN,THERESA J.; WIRTH,SHARON

1999-09-01T23:59:59.000Z

433

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

434

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

435

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

436

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

437

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

438

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

439

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

440

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

Note: This page contains sample records for the topic "rates disposable income" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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441

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

442

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

443

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

444

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

445

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

446

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

447

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

448

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

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. 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 U.S. 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 has implemented 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. The LTSP is based on the UMTRA Project`s long-term surveillance program guidance and meets the requirements of 10 CFR 40.27(b) and 40 CFR 192.03.

NONE

1997-03-01T23:59:59.000Z

449

Z-Area saltstone disposal facility groundwater monitoring report. First and second quarters 1997  

SciTech Connect (OSTI)

This report presents the results of groundwater sampling during the first and second quarters of 1997 in the Z-Area Saltstone Disposal Facility. This report presents only the data for sampling during the first half of 1997 as required by industrial Solid Waste Permit No. 025500-1603. For a detailed discussion of groundwater monitoring in the Z-Area Saltstone Disposal Facility, consult the 1996 Z-Area Saltstone Disposal Annual Report. Appendix A presents the proposed South Carolina Department of Health and Environmental Control Proposed Groundwater Monitoring Standards. Flagging criteria are described in Appendix B. In May 1997 SCDHEC granted approval for seven hydrocone sampling.

NONE

1997-07-01T23:59:59.000Z

450

Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1  

SciTech Connect (OSTI)

This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, administration facility, weigh scale, and various staging/storage areas. These facilities were designed and constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the Idaho National Laboratory (INL) facility for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams.

Simonds, J.

2007-11-06T23:59:59.000Z

451

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

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Ambrosia Lake disposal site in McKinley County, New Mexico, describes the U.S. Department of Energy`s (DOE) long-term care program for the disposal site. The DOE will carry out this program to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials.

NONE

1996-07-01T23:59:59.000Z

452

Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah  

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 Mexican Hat, Utah, disposal site. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Mexican Hat disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP.

NONE

1997-06-01T23:59:59.000Z

453

Impact of 2001 Building Technology, state and community programs on United States employment and wage income  

SciTech Connect (OSTI)

The Department of Energy Office of Building Technology, State and Community Programs (BTS) is interested in assessing the potential economic impacts of its portfolio of programs on national employment and income. A special purpose version of the IMPLAN input-output model allied In Build is used in this study of all 38 BTS programs included in the FY2001 federal budget. Energy savings, investments, and impacts on U.S. national employment and wage income are reported by program for selected years to the year 2030. Energy savings from these programs have the potential of creating a total of nearly 332,000 jobs and about $5.3 billion in wage income (1995$) by the year 2030. Because the required investments to achieve these savings are capital intensive, the net effect after investment is 304,000 jobs and $5.0 billion.

MJ Scott; DJ Hostick; DB Elliott

2000-03-20T23:59:59.000Z

454

Impact of the FY 2005 Weatherization and Intergovernmental Program on United States Employment and Earned Income  

SciTech Connect (OSTI)

The Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) is interested in assessing the potential economic impacts of its portfolio of subprograms on national employment and income. A special purpose version of the IMPLAN input-output model called ImBuild II is used in this study of 20 subprograms of the Weatherization and Intergovernmental Program contained in the EERE final FY 2005 budget request to the Office of Management and Budget on February 2, 2004. Energy savings, investments, and impacts on U.S. national employment and earned income are reported by subprogram for selected years to the year 2030. Energy savings and investments from these subprograms have the potential of creating a total of 228,000 jobs and about $3.1 billion in earned income (2003$) by the year 2030.

Scott, Michael J.; Anderson, David M.; Belzer, David B.; Cort, Katherine A.; Dirks, James A.; Elliott, Douglas B.; Hostick, Donna J.

2004-08-31T23:59:59.000Z

455

Impact of the FY 2005 Building Technologies Program on United States Employment and Earned Income  

SciTech Connect (OSTI)

The Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) is interested in assessing the potential economic impacts of its portfolio of subprograms on national employment and income. A special purpose version of the IMPLAN input-output model called ImBuild II is used in this study of all 21 Building Technologies Program subprograms in the EERE final FY 2005 budget request to the Office of Management and Budget on February 2, 2004. Energy savings, investments, and impacts on U.S. national employment and earned income are reported by subprogram for selected years to the year 2030. Energy savings and investments from these subprograms have the potential of creating a total of 396,000 jobs and about $5.6 billion in earned income (2003$) by the year 2030.

Scott, Michael J.; Anderson, Dave M.; Belzer, David B.; Cort, Katherine A.; Dirks, James A.; Elliott, Douglas B.; Hostick, Donna J.

2004-08-31T23:59:59.000Z

456

Impact of the FY 2009 Building Technologies Program on United States Employment and Earned Income  

SciTech Connect (OSTI)

The Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) is interested in assessing the potential economic impacts of its portfolio of subprograms on national employment and income. A special purpose input-output model called ImSET is used in this study of 14 Building Technologies Program subprograms in the EERE final FY 2009 budget request to the Office of Management and Budget in February 2008. Energy savings, investments, and impacts on U.S. national employment and earned income are reported by subprogram for selected years to the year 2025. Energy savings and investments from these subprograms have the potential of creating a total of 258,000 jobs and about $3.7 billion in earned income (2007$) by the year 2025.

Livingston, Olga V.; Scott, Michael J.; Hostick, Donna J.; Dirks, James A.; Cort, Katherine A.

2008-06-17T23:59:59.000Z

457

Low-income energy policy in a restructuring electricity industry: an assessment of federal options  

SciTech Connect (OSTI)

This report identifies both the low-income energy services historically provided in the electricity industry and those services that may be affected by industry restructuring. It identifies policies that are being proposed or could be developed to address low- income electricity services in a restructured industry. It discusses potential federal policy options and identifies key policy and implementation issues that arise when considering these potential federal initiatives. To understand recent policy development at the state level, we reviewed restructuring proposals from eight states and the accompanying testimony and comments filed in restructuring proceedings in these states.

Baxter, L.W.

1997-07-01T23:59:59.000Z

458

Process For Controlling Flow Rate Of Viscous Materials Including Use Of Nozzle With Changeable Openings  

DOE Patents [OSTI]

Apparatus and a method for controlling the flow rate of viscous materials through a nozzle includes an apertured main body and an apertured end cap coupled together and having an elongated, linear flow channel extending the length thereof. An end of the main body is disposed within the end cap and includes a plurality of elongated slots concentrically disposed about and aligned with the flow channel. A generally flat cam plate having a center aperture is disposed between the main body and end cap and is rotatable about the flow channel. A plurality of flow control vane assemblies are concentrically disposed about the flow channel and are coupled to the cam plate. Each vane assembly includes a vane element disposed adjacent the end of the flow channel. Rotation of the cam plate in a first direction causes a corresponding rotation of each of the vane elements for positioning the individual vane elements over the aperture in the end cap blocking flow through the flow channel, while rotation in an opposite direction removes the vane elements from the aperture and positions them about the flow channel in a nested configuration in the full open position, with a continuous range of vane element positions available between the full open and closed positions.

Ellingson, William A. (Naperville, IL); Forster, George A. (Westmont, IL)

1999-11-02T23:59:59.000Z

459

Selected biological investigations on deep sea disposal of industrial wastes  

E-Print Network [OSTI]

shrimp bioassay summary. Dinoflagellate bioassay summary. Diatom bioassay summary. Summary of 96-hour TL bioassay results. 25 28 30 33 viii LIST OF FIGURES Number ~Pa e Growth of control showing logarithmic rate. Waste concentration decrease.... To date, funds have been available only for short- term studies that have been directed toward specific questions such as maximum discharge rates and short-term toxic effects on marine organisms. Hood and his associates (1958) at Texas A&M University...

Page, Sandra Lea

1975-01-01T23:59:59.000Z

460

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

Note: This page contains sample records for the topic "rates disposable income" 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

Thermoplastic Microfluidic Device for On-Chip Purification of Nucleic Acids for Disposable  

E-Print Network [OSTI]

Thermoplastic Microfluidic Device for On-Chip Purification of Nucleic Acids for Disposable, Brookline, Massachusetts 02446 A polymeric microfluidic device for solid-phase extraction (SPE applications. Microfluidic approaches to nucleic acid isolation have therefore received great attention

462

An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes  

E-Print Network [OSTI]

Deep boreholes, 3 to 5 km into igneous rock, such as granite, are evaluated for next- generation repository use in the disposal of spent nuclear fuel and other high level waste. The primary focus is on the stability and ...

Anderson, Victoria Katherine, 1980-

2004-01-01T23:59:59.000Z

463

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

Broader source: Energy.gov [DOE]

The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division...

464

Effective thermal conductivity measurements relevant to deep borehole nuclear waste disposal  

E-Print Network [OSTI]

The objective of this work was to measure the effective thermal conductivity of a number of materials (particle beds, and fluids) proposed for use in and around canisters for disposal of high level nuclear waste in deep ...

Shaikh, Samina

2007-01-01T23:59:59.000Z

465

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal...  

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

to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine Gelles*, U.S. Department of Energy ; Edward Regnier, U.S. Department of Energy; Andrew Wallo,...

466

E-Print Network 3.0 - assess waste disposal Sample Search Results  

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

the University is implementing a charge to fund the costs of handling and disposal of "E-Waste." As previously... : Tuesday, December 23, 2008 Re: Notice of E-Waste Charge,...

467

Regional Examples of Geological Settings for Nuclear Waste Disposal in Deep Boreholes  

E-Print Network [OSTI]

This report develops and exercises broad-area site selection criteria for deep boreholes suitable for disposal of spent nuclear fuel and/or its separated constituents. Three candidates are examined: a regional site in the ...

Sapiie, B.

468

South Florida Sun-Sentinel.com Seaweed invasion creates disposal problem  

E-Print Network [OSTI]

Beach, said it's impossible to haul tons of seaweed off these beaches for disposal because there are few access points for trucks. The company has begun raking the seaweed into the beach, mixing it with the top

Belogay, Eugene A.

469

Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...  

Office of Environmental Management (EM)

of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did...

470

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

2009-03-01T23:59:59.000Z

471

Risk assessment involving the land disposal of animal waste on Central Texas dairies  

E-Print Network [OSTI]

Land disposal of animal waste is an increasing problem for dairies in central Texas Once isolated, many producers now and themselves surrounded by towns and subdivisions. Many of these new neighbors are showing an increasing concern about potential...

Lee, Thomas Chadwick

1999-01-01T23:59:59.000Z

472

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 U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents the land ownership interests and details how the long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

Not Available

1994-09-01T23:59:59.000Z

473

E-Print Network 3.0 - alcatraz disposal site Sample Search Results  

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

FLOOD PLAIN AREA CLEANUP FACT SHEET & PROJECT SUMMARY Summary: the excavated pond-area soils from the Site for off-site disposal. The pond area was released for unrestricted......

474

Criteria for releases and disposal of low level and intermediate level waste in Sweden  

SciTech Connect (OSTI)

In Sweden there exists a complete system for management, including final disposal, of all radioactive wastes which are not classified as long-lived or high-level waste. This paper will present the disposal options and the requirements set on the waste categories as well as Sweden`s four different engineered shallow land disposals. The advantages of having a shallow land disposal together with exemption of waste and a final storage facility for low-level and intermediate-level waste are discussed. Finally, the paper will give a summary of why Sweden has succeeded in establishing a full system for low-level and intermediate-level waste. The discussion is from regulatory point of view.

Lindbom, G. [Swedish Radiation Protection Inst., Stockholm (Sweden). Div. of Waste Management and Environmental Protection

1993-12-31T23:59:59.000Z

475

Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Recovery Act Funds  

Broader source: Energy.gov [DOE]

The Moab Uranium Mill Tailings Remedial Action Project reached its primary American Recovery and Reinvestment Act milestone ahead of schedule on Wednesday with the disposal of 2 million tons of...

476

Dynamics of particle clouds in ambient currents with application to open-water sediment disposal  

E-Print Network [OSTI]

Open-water sediment disposal is used in many applications around the world, including land reclamation, dredging, and contaminated sediment isolation. Timely examples include the land reclamation campaign currently underway ...

Gensheimer, Robert James, III

2010-01-01T23:59:59.000Z

477

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

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to continue the on-site disposal of solid waste at the Area 9 and Area 23 landfills at the U.S. Department of Energy Nevada Test Site...

478

Management Policy for Planning, Programming, Budgeting, Operation, Maintenance and Disposal of Real Property  

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

To establish Department of Energy (DOE) management policy for the planning, programming, budgeting, operation, maintenance and disposal of real property owned by the United States and under the custody and control of DOE.

2002-05-20T23:59:59.000Z